cv.bib

@inproceedings{chee_demand_2019,
	address = {Champaign, IL},
	title = {Demand {Driven} {Deployment} {Capabilities} in {Cyclus}},
	url = {arfc.github.io/twofcs19},
	abstract = {For many fuel cycle simulators, it is currently up to the user to define a deployment scheme of supporting facilities or provide an infinite inventory of commodities to ensure that there is no gap in the supply chain. To ease setting up nuclear fuel cycle simulations, Nuclear Fuel Cycle (NFC) simulators should bring demand responsive deployment decisions into the dynamics of the simulation logic. In this work, we develop demand driven deployment capabilities in Cyclus, d3ploy. User-controlled capabilities such as supply/ capacity buffers, constraint deployment, prediction algorithms, and installed capacity deployment were introduced in d3ploy to give a user the tools to minimize commodity undersupply in a simulation. We demonstrate d3ploy{\textquoteright}s capability to automatically deploy fuel cycle facilities to meet various types of user-defined power demands: constant, linearly increasing, and sinusoidal.},
	booktitle = {Proceedings of the {Technical} {Workshop} on {Fuel} {Cycle} {Simulation} 2019},
	author = {Chee, Gwendolyn J.},
	collaborator = {Flanagan, Robert R. and Huff, Kathryn D},
	month = jun,
	year = {2019},
	file = {2019-chee-twofcs-pres.pdf:/Users/huff/Zotero/storage/V95BLIN6/2019-chee-twofcs-pres.pdf:application/pdf;2019-chee-twofcs-pres.pptx:/Users/huff/Zotero/storage/N49L9PAI/2019-chee-twofcs-pres.pptx:application/vnd.openxmlformats-officedocument.presentationml.presentation},
}

@inproceedings{huff_demand_2019,
	address = {Argonne, IL, United States},
	title = {Demand {Driven} {Cycamore} {Archetypes} {FY16} {NEUP} {Award} {Summary}},
	booktitle = {Presentations in the {DOE}-{NE} {Systems} {Analysis} and {Integration} ({SA}\&{I}) {Campaign}},
	author = {Huff, Kathryn D.},
	month = sep,
	year = {2019},
}

@article{carlsen_cycamore_2014,
	title = {Cycamore v1.0.0},
	url = {http://figshare.com/articles/Cycamore_v1_0_0/1041829},
	doi = {http://figshare.com/articles/Cycamore_v1_0_0/1041829},
	abstract = {Additional module for Cyclus, the nuclear fuel cycle simulator developed at the University of Wisconsin - Madison, supporting the modeling of innovative fuel cycles.},
	urldate = {2014-06-03},
	journal = {Figshare},
	author = {Carlsen, Robert W. and Gidden, Matthew and Huff, Kathryn and Opotowsky, Arrielle C. and Rakhimov, Olzhas and Scopatz, Anthony M. and Wilson, Paul},
	month = jun,
	year = {2014},
	note = {http://figshare.com/articles/Cycamore\_v1\_0\_0/1041829},
	keywords = {Nuclear Fuel Cycle, agent-based simulation},
	file = {cycamore_1.0.0:/Users/huff/Zotero/storage/W2VGZTDV/Scopatz et al. - 2014 - Cycamore v1.0.0:application/zip;Figshare Download:/Users/huff/Zotero/storage/WQD2B5KA/Scopatz et al. - 2014 - Cycamore v1.0.0:application/zip;Figshare Snapshot:/Users/huff/Zotero/storage/N44XFGRX/Scopatz et al. - 2014 - Cycamore v1.0.0.html:text/html;Full Text (HTML):/Users/huff/Zotero/storage/H56U7DUZ/Scopatz et al. - 2014 - Cycamore v1.0.0.html:text/html},
}

@misc{turkmen_machine-learning-enabled_2019,
	address = {Columbus, OH},
	type = {Workshop},
	title = {Machine-{Learning}-{Enabled} {Design} for {Molten} {Salt} {Reactors}},
	url = {https://github.com/arfc/2019-12-bigdata-npps},
	abstract = {Nuclear reactor design can improve economics, safety, breeding capability, and operational flexibility.
Accordingly, we introduce an efficient, robust, and reliable design recommendation approach based on
machine learning methods. This approach explores seven independent input parameters in the context of a
single fuel channel of Molten Salt Fast Reactor, including fissile material (U, U/Pu, U/Th), salt type (Na,
Cl, F), enrichment, channel pitch, channel length, moderator-to-salt ratio, and channel power (or channel
outlet temperature). Performance metric for optimization include kinf , the conversion ratio ($\gamma$), feedback
coefficients ($\alpha$D , $\alpha$V , $\alpha$M ), and the fast flux incident on graphite material. Optimization, data mining and
sampling in this work will rely on the RAVEN framework, developed by the Idaho National Laboratory,
to produce the datasets, to explore the parameter space, and to train a model for recommending design
optimization. The tool created in this work couples to the SERPENT neutron transport software to
compute these design performance metrics. We expect this tool will make significant contributions to core
design optimization by exposing multitudinous possible scenarios, facilitating decision making, accelerating
the design process and reducing the man-hours consumed in modeling.},
	author = {Turkmen, Mehmet},
	collaborator = {Huff, Kathryn D.},
	month = dec,
	year = {2019},
	file = {Turkmen - 2019 - Machine-Learning-Enabled Design for Molten Salt Re.pdf:/Users/huff/Zotero/storage/54ABMGRC/Turkmen - 2019 - Machine-Learning-Enabled Design for Molten Salt Re.pdf:application/pdf},
}

@phdthesis{kamuda_automated_2019,
	address = {Urbana, IL},
	type = {{PhD} {Dissertation}},
	title = {Automated {Isotope} {Identification} and {Quantification} {Using} {Artificial} {Neural} {Networks}},
	shorttitle = {Automated {Isotope} {Identification} and {Quantification} {Using} {Artificial} {Neural} {Networks}},
	abstract = {Current radioisotope identification devices struggle to identify and quantify isotopes in low-resolution gamma-ray spectra in a wide range of realistic conditions. Trained gamma-ray spectroscopists typically rely on intuition when identifying isotopes in spectra. A trained gamma-ray spectroscopist can inject their intuition into pattern recognition algorithms by creating training datasets and intelligently choosing a machine learning model for a task. Algorithms based on feature extraction such as peak finding or ROI algorithms work well for well-calibrated high resolution detectors. For low-resolution detectors, it may be more beneficial to use algorithms that incorporate more abstract features of the spectrum. To investigate this, we simulated datasets and used them to train artificial neural networks (ANNs) for identification and quantification tasks using gamma-ray spectra. Because the datasets were simulated, this method can be extended to a variety of gamma-ray spectroscopy tasks. Models weinvestigated include dense, convolutional, and autoencoder ANNs. In this work we introduce annsa, an open source Python package capable of creating gamma-ray spectroscopy training datasets and applying machine learning models to solve spectroscopic tasks. Using annsa, we found that identification performance in simulated spectra was sensitive to the source-to-background ratio, detector gain setting, and shielding. Performance was less sensitive to the source-detector height and detector resolution. We demonstrate annsa{\textquoteright}s capabilities on a source inter-
diction classification problem, outperforming a peak-based Bayesian classifier for source identification. We also demonstrate annsa on a uranium enrich-
ment quantification problem which shows an accuracy useful for homeland security applications.},
	language = {English},
	school = {University of Illinois at Urbana-Champaign},
	author = {Kamuda, Mark},
	month = nov,
	year = {2019},
	file = {Kamuda - 2019 - Automated Isotope Identification and Quantificatio.pdf:/Users/huff/Zotero/storage/WQHLJA5K/Kamuda - 2019 - Automated Isotope Identification and Quantificatio.pdf:application/pdf},
}

@article{bae_deep_2020,
	title = {Deep learning approach to nuclear fuel transmutation in a fuel cycle simulator},
	volume = {139},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454919307406},
	doi = {10.1016/j.anucene.2019.107230},
	abstract = {We trained a neural network model to predict Pressurized Water Reactor (PWR) Used Nuclear Fuel (UNF) composition given initial enrichment and burnup. This quick, flexible, medium-fidelity method to estimate depleted PWR fuel assembly compositions is used to model scenarios in which the PWR fuel burnup and enrichment vary over time. The Used Nuclear Fuel Storage, Transportation \& Disposal Analysis Resource and Data System (UNF-ST\&DARDS) Unified Database (UDB) provided a ground truth on which the model trained. We validated the model by comparing the U.S. UNF inventory profile predicted by the model with the UDB UNF inventory profile. The neural network yields less than 1\% error for UNF inventory decay heat and activity and less than 2\% error for major isotopic inventory. The neural network model takes 0.27 s for 100 predictions, compared to 118 s for 100 Oak Ridge Isotope GENeration (ORIGEN) calculations. We also implemented this model into Cyclus, an agent-based Nuclear Fuel Cycle (NFC) simulator, to perform rapid, medium-fidelity PWR depletion calculations. This model also allows discharge of batches with assemblies of varying burnup. Since the original private data cannot be retrieved from the model, this trained model can provide open-source depletion capabilities to NFC simulators. We show that training an artificial neural network with a dataset from a complex fuel depletion model can provide rapid, medium-fidelity depletion capabilities to large-scale fuel cycle simulations.},
	language = {en},
	urldate = {2020-01-07},
	journal = {Annals of Nuclear Energy},
	author = {Bae, Jin Whan and Rykhlevskii, Andrei and Chee, Gwendolyn and Huff, Kathryn D.},
	month = may,
	year = {2020},
	keywords = {Simulation, Depletion, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Parallel computing, Reactor physics, Molten salt breeder reactor, Molten salt reactor, Online reprocessing, Python, Salt treatment, Artificial neural network, Machine learning, Spent nuclear fuel},
	pages = {107230},
	file = {Bae et al. - 2020 - Deep learning approach to nuclear fuel transmutati.pdf:/Users/huff/Zotero/storage/63AWUGKG/63AWUGKG.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/U7IJI82D/S0306454919307406.html:text/html},
}

@techreport{rykhlevskii_milestone_2019,
	address = {Urbana, IL},
	type = {Milestone {Report}},
	title = {Milestone 2.1 {Report}: {Demonstration} of {SaltProc}},
	shorttitle = {Contract {DE}-{AR0000983}, {Enabling} {Load} {Following} {Capability} in the {Transatomic} {MSR}},
	abstract = {The University of Illinois, Urbana-Champaign (UIUC) is engaged in work to develop a fuel processing system that enables load-following in Molten Salt Reactors (MSRs), an important ability that allows nuclear power plants to ramp electricity production up or down to meet changing electricity demand. Nuclear reactions in MSRs produce unwanted byproducts (such as xenon and krypton) that can adversely affect power production. In steady, baseload operation, these byproducts form and decay at the same rate. When electricity production is ramped down, however, the byproducts start to be produced at a greater rate than they decay, leading to a buildup within the reactor. When power production must be once again increased, the response rate is slowed by the time needed for the byproducts to reach their equilibrium level (determined by the radioactive decay half-life, which is on the order of hours). Thus, buildup of these unwanted byproducts resulting from ramping down inhibit proper load following for molten salt reactors. Fortunately, MSRs transport fuel in a flowing molten salt fuel loop, which means that a section of the reactor, outside the core, can be leveraged for fuel processing and "cleanup." The team will determine the feasibility of removal of these unwanted byproducts and de- sign a fuel reprocessing system, removing a major barrier to commercialization for molten salt reactors.

Toward this work, we initiated the Fuel Cycle Simulation task (Task 2) in August 2018 to more realistically model the online reprocessing system of the Transatomic Power (TAP) MSR. A Python toolkit, SaltProc v0.1 [1{\textendash}3], was developed to represent the simplified online fuel salt processing of a Molten Salt Breeder Reactor (MSBR). More recently, an advanced SaltProc version (SaltProc v0.2) was developed to generically simulate complex molten salt fuel reprocessing systems, including the TAP system, incorporating user-parametrized components into the fuel salt processing design. This report summarizes the progress we have made towards milestone M2.1: Demonstrate SaltProc and the steps toward the subsequent Task 2 objectives.},
	language = {english},
	number = {UIUC-ARFC-2019-04 DOI: 10.5281/zenodo.3355649},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Rykhlevskii, Andrei and Huff, Kathryn},
	month = jun,
	year = {2019},
	doi = {10.5281/zenodo.3355649},
	keywords = {cyclus, nuclear engineering, arfc, report, molten salt reactor, nuclear fuel cycle},
	pages = {1--23},
	annote = {This research is being performed using funding received from the Department of Energy ARPA-E MEITNER Program (award DE-AR0000983) and the Blue Waters sustained-petascale computing project, which is supported by the National Science Foundation (awards OCI-0725070 and ACI-1238993) and the state of Illinois. Blue Waters is a joint effort of the University of Illinois at Urbana-Champaign and its National Center for Supercomputing Applications.},
	annote = {This research is being performed using funding received from the Department of Energy ARPA-E MEITNER Program (award DE-AR0000983) and the Blue Waters sustained-petascale computing project, which is supported by the National Science Foundation (awards OCI-0725070 and ACI-1238993) and the state of Illinois. Blue Waters is a joint effort of the University of Illinois at Urbana-Champaign and its National Center for Supercomputing Applications.},
	annote = {This research is being performed using funding received from the Department of Energy ARPA-E MEITNER Program (award DE-AR0000983) and the Blue Waters sustained-petascale computing project, which is supported by the National Science Foundation (awards OCI-0725070 and ACI-1238993) and the state of Illinois. Blue Waters is a joint effort of the University of Illinois at Urbana-Champaign and its National Center for Supercomputing Applications.},
	file = {Huff - 2019 - Milestone 2.1 Report Demonstration of SaltProc.pdf:/Users/huff/Zotero/storage/WJUPG67I/Huff - 2019 - Milestone 2.1 Report Demonstration of SaltProc.pdf:application/pdf;Zenodo Full Text PDF:/Users/huff/Zotero/storage/ZFLGME7X/Andrei Rykhlevskii and Kathryn Huff - 2019 - Milestone 2.1 Report Demonstration of SaltProc.pdf:application/pdf;Zenodo Full Text PDF:/Users/huff/Zotero/storage/RYZ3VPVQ/Andrei Rykhlevskii and Kathryn Huff - 2019 - Milestone 2.1 Report Demonstration of SaltProc.pdf:application/pdf;Zenodo Full Text PDF:/Users/huff/Zotero/storage/BN8EED2W/Andrei Rykhlevskii and Kathryn Huff - 2019 - Milestone 2.1 Report Demonstration of SaltProc.pdf:application/pdf},
}

@inproceedings{chee_demonstration_2019,
	address = {Seattle, WA, United States},
	title = {Demonstration of {Demand}-{Driven} {Deployment} {Capabilities} in {Cyclus}},
	url = {http://epubs.ans.org/?a=46949},
	booktitle = {Proceedings of {Global}/{Top} {Fuel} 2019},
	publisher = {American Nuclear Society},
	author = {Chee, Gwendolyn and Bae, Jin Whan and Huff, Kathryn D. and Flanagan, Robert R. and Fairhurst, Roberto},
	month = sep,
	year = {2019},
	pages = {394--401},
	file = {Chee et al. - 2019 - Demonstration of Demand-Driven Deployment Capabili.pdf:/Users/huff/Zotero/storage/DAS8F5HF/Chee et al. - 2019 - Demonstration of Demand-Driven Deployment Capabili.pdf:application/pdf},
}

@inproceedings{flanagan_methods_2019,
	address = {Seattle, WA, United States},
	title = {Methods for {Automated} {Fuel} {Cycle} {Facility} {Deployment}},
	url = {http://epubs.ans.org/?a=46950},
	booktitle = {Proceedings of {Global}/{Top} {Fuel} 2019},
	publisher = {American Nuclear Society},
	author = {Flanagan, Robert R. and Bae, Jin Whan and Huff, Kathryn D. and Chee, Gwendolyn J. and Fairhurst, Roberto},
	month = sep,
	year = {2019},
	pages = {402--427},
	file = {Flanagan et al. - 2019 - Methods for Automated Fuel Cycle Facility Deployme.pdf:/Users/huff/Zotero/storage/8IBKW5LD/Flanagan et al. - 2019 - Methods for Automated Fuel Cycle Facility Deployme.pdf:application/pdf},
}

@inproceedings{huff_current_2017,
	address = {Seoul, South Korea},
	title = {Current {Status} of {Predictive} {Transition} {Capability} in {Fuel} {Cycle} {Simulation}},
	url = {https://books.google.com/books/about/GLOBAL_2017.html?id=1UjsuQEACAAJ},
	abstract = {Nuclear fuel cycle simulation scenarios are most naturally described as 
constrained objective functions. The objectives are often systemic 
demands such as ``achieve 1\% growth for total electricity production 
and reach 10\% uranium utilization''. The constraints take 
the form of nuclear fuel cycle technology availability 
(``reprocessing begins after 2025 and fast reactors first become 
available in 2050'').

To match the natural constrained objective form of the scenario 
definition, NFC simulators must bring demand responsive 
deployment decisions into the dynamics of the simulation logic.

In particular, a NFC simulator should have the 
capability to deploy supporting fuel cycle facilities to enable 
a demand to be met. Take, for instance, the standard once through fuel 
cycle. Reactors may be deployed to meet a objective power demand. 
However, new mines, mills, and enrichment facilities will also need to be 
deployed to ensure that reactors have sufficient fuel to produce power.  
In many simulators, the unrealistic solution to this problem is to 
simply have infinite capacity support facilities. Alternatively, 
detailing the deployment timeline of all facilities becomes the 
responsibility of the user.

The authors seek to identify the most flexible, general, and performant 
algorithms applicable to this modeling challenge.  Accordingly, a review was 
conducted of current NFC simulation tools to determine the 
current capabilites for demand-driven and transition scenarios. 
Additionally, the authors investigated promising algorithmic
innovations that have been successful for similar applications in other domains
such as economics and industrial engineering.},
	language = {en},
	booktitle = {Proceedings of {Global} 2017},
	publisher = {American Nuclear Society},
	author = {Huff, Kathryn D. and Bae, Jin Whan and Mummah, Kathryn A. and Flanagan, Robert R. and Scopatz, Anthony M.},
	month = sep,
	year = {2017},
	file = {Huff et al. - 2017 - Current Status of Predictive Transition Capability.pdf:/Users/huff/Zotero/storage/CDQJ8KB8/Huff et al. - 2017 - Current Status of Predictive Transition Capability.pdf:application/pdf;Huff et al. - Current Status of Predictive Transition Capability.pdf:/Users/huff/Zotero/storage/LE3726S6/Huff et al. - Current Status of Predictive Transition Capability.pdf:application/pdf},
}

@article{lindsay_introduction_2018,
	title = {Introduction to {Moltres}: {An} application for simulation of {Molten} {Salt} {Reactors}},
	volume = {114},
	issn = {0306-4549},
	shorttitle = {Introduction to {Moltres}},
	url = {https://linkinghub.elsevier.com/retrieve/pii/S0306454917304760},
	doi = {10.1016/j.anucene.2017.12.025},
	abstract = {Moltres is a new physics application for modeling coupled physics in fluid-fuelled, molten salt reactors. This paper describes its neutronics model, thermal hydraulics model, and their coupling in the MOOSE framework. Neutron and precursor equations are implemented using an action system that allows use of an arbitrary number of groups with no change in the input card. Results for many-channel configurations in 2D-axisymmetric and 3D coordinates are presented and compared against other coupled models as well as the Molten Salt Reactor Experiment.},
	language = {en},
	urldate = {2018-01-08},
	journal = {Annals of Nuclear Energy},
	author = {Lindsay, Alexander and Ridley, Gavin and Rykhlevskii, Andrei and Huff, Kathryn},
	month = apr,
	year = {2018},
	keywords = {Simulation, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Parallel computing, Reactor physics},
	pages = {530--540},
	annote = {2d prescribed},
	file = {Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:/Users/huff/Zotero/storage/RCWUNGTP/Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf;Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:/Users/huff/Zotero/storage/3GEC6NQ9/Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf;Moltres.pdf:/Users/huff/Zotero/storage/4XDXRICB/Moltres.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/E2T9U5IX/Lindsay et al. - 2018 - Introduction to Moltres An application for simula.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/3DT9TEY3/S0306454917304760.html:text/html},
}

@article{bae_synergistic_2019,
	title = {Synergistic spent nuclear fuel dynamics within the {European} {Union}},
	volume = {114},
	issn = {0149-1970},
	url = {http://www.sciencedirect.com/science/article/pii/S014919701930037X},
	doi = {10.1016/j.pnucene.2019.02.001},
	abstract = {The French 2012{\textendash}2015 Commission Nationale d{\textquoteright}Evaluation Reports emphasize preparation for a transition from Light Water Reactors (LWRs) to Sodium-Cooled Fast Reactors (SFRs). We used the Cyclus nuclear fuel cycle simulator to explore the feasibility of enabling a French transition to an SFR fleet by using Used Nuclear Fuel (UNF) from other European Union (EU) nations. A Cyclus simulation captured nuclear power deployment in the EU from 1970 to 2160. In this simulation, France begins its planned transition to SFRs as existing LWRs are decommissioned. These SFRs are fueled with UNF accumulated by other EU nations and reprocessed in France. The impact of reactor lifetime extensions and SFR breeding ratios on time-to-transition were investigated with additional simulations. These simulations demonstrate that France can avoid deployment of additional LWRs by accepting UNF from other EU nations, that lifetime extensions delay time-to-transition, and improved breeding ratios are not particularly impactful.},
	urldate = {2019-04-15},
	journal = {Progress in Nuclear Energy},
	author = {Bae, Jin Whan and Singer, Clifford E. and Huff, Kathryn D.},
	month = jul,
	year = {2019},
	keywords = {Simulation, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Parallel computing, Reactor physics, Transition, Spent nuclear fuel, Agent-based, European union},
	pages = {1--12},
	file = {Bae et al. - 2018 - Synergistic Spent Nuclear Fuel Dynamics Within the.pdf:/Users/huff/Zotero/storage/3QBIMRIH/Bae et al. - 2018 - Synergistic Spent Nuclear Fuel Dynamics Within the.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/FUTLQJAP/Bae et al. - 2019 - Synergistic spent nuclear fuel dynamics within the.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/E9FXRY45/S014919701930037X.html:text/html},
}

@book{scopatz_effective_2015,
	address = {Sebastopol, CA},
	edition = {1},
	title = {Effective computation in physics: {Field} guide to research with python},
	isbn = {978-1-4919-0153-3},
	shorttitle = {Effective computation in physics},
	url = {http://shop.oreilly.com/product/0636920033424.do},
	abstract = {Effective Computation in Physics is a handy guide to the types of problems you run into with computational physics{\textemdash}such as version control, bash scripts, object orientation, large databases, and parallel machines. The authors provide detailed scientific computing motivations, clear and concise tutorials, and references to further information about each of the topics presented.This book fills the existing training gap for students and scientists who conduct physics in a world where simulations have replaced desktop experiments and sophisticated data traversing algorithms have replaced pen and paper analysis.Provides a central source that ties various pieces of computational physics togetherContains coverage of the Python programming language aimed toward physicistsHelps you properly analyze and compellingly visualize your dataIncludes chapters on hot topics like NumPy and HDF5},
	language = {English},
	publisher = {O'Reilly Media},
	author = {Scopatz, Anthony M. and Huff, Kathryn D.},
	month = may,
	year = {2015},
	file = {Scopatz and Huff - 2015 - Effective computation in physics Field guide to r.pdf:/Users/huff/Zotero/storage/33KZQE9J/Scopatz and Huff - 2015 - Effective computation in physics Field guide to r.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/N9AQ2CIB/books.html:text/html;Snapshot:/Users/huff/Zotero/storage/HHETCY3D/books.html:text/html},
}

@article{huff_rapid_2017,
	title = {Rapid methods for radionuclide contaminant transport in nuclear fuel cycle simulation},
	volume = {114},
	issn = {0965-9978},
	doi = {10.1016/j.advengsoft.2017.07.006},
	abstract = {Nuclear fuel cycle and nuclear waste disposal decisions are technologically coupled. However, current nuclear fuel cycle simulators lack dynamic repository performance analysis due to the computational burden of high-fidelity hydrolgic contaminant transport models. The Cyder disposal environment and repository module was developed to fill this gap. It implements medium-fidelity hydrologic radionuclide transport models to support assessment appropriate for fuel cycle simulation in the Cyclus fuel cycle simulator. Rapid modeling of hundreds of discrete waste packages in a geologic environment is enabled within this module by a suite of four closed form models for advective, dispersive, coupled, and idealized contaminant transport: a Degradation Rate model, a Mixed Cell model, a Lumped Parameter model, and a 1-D Permeable Porous Medium model. A summary of the Cyder module, its timestepping algorithm, and the mathematical models implemented within it are presented. Additionally, parametric demonstrations simulations performed with Cyder are presented and shown to demonstrate functional agreement with parametric simulations conducted in a standalone hydrologic transport model, the Clay Generic Disposal System Model developed by the Used Fuel Disposition Campaign Department of Energy Office of Nuclear Energy.},
	urldate = {2019-03-03},
	journal = {Advances in Engineering Software},
	author = {Huff, Kathryn},
	month = dec,
	year = {2017},
	keywords = {Simulation, Nuclear Fuel Cycle, Repository, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Hydrologic contaminant transport, nuclear engineering, simulation},
	pages = {268--281},
	annote = {Discussion of what models are used for radionuclide contaminant transport and essentially how the code works. It also discusses the significance of repository modeling.
Significance
- Nuclear fuel cycle and nuclear waste disposal decisions are technologically coupled through the characteristics of spent fuel which vary among fuel cycles and impact repository design and performance
- Dynamic integration of generic disposal model with fuel cycle systems analysis framework is necessary to illuminate performance distinctions of candidate repository host media, designs, and engineering components in the context of fuel cycle options
- Most current tools treat waste disposal phase of fuel cycle analysis statically in post processing by reporting values such as mass, volumes, radiotoxicity, or heat production of accumulated SNF and high level waste. They fail to address the dynamic impact of the waste streams on the performance of the geologic disposal system.
~
Cyder
- Cyder provides medium fidelity models to conduct repository performance analysis on efficient timescales appropriate for fuel cycle analyses},
	file = {ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/PMST2RA5/PMST2RA5.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/XR4V3VZV/Huff - Rapid methods for radionuclide contaminant transpo.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/27XJEXE8/S0965997817302703.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/34UH4PHR/S0965997817302703.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/ZETJXGMB/S0965997817302703.html:text/html},
}

@misc{huff_neutron_2019,
	address = {Spokane, WA},
	type = {Invited {Minisyposium} {Talk}},
	title = {Neutron {Kinetics} in {Liquid}-{Fueled} {Nuclear} {Reactors}},
	url = {https://katyhuff.github.io/2018-02-25-siam},
	abstract = {Modeling and simulation of neutron kinetics in liquid-fueled nuclear reactors incorporates three major challenging components. First, it is necessary to establish the dynamic evolution of fuel composition via depletion and online reprocessing. Additionally, multiphysics analysis of the thermal hydraulics and neutronics in such a reactor must incorporate thermal feedbacks and material expansion feedbacks. Finally, drift of delayed neutron precursors must be incorporated into the kinetics analysis due to the mobility of the liquid fuel. This talk will discuss all three components. Toward the first component, a discussion of the SaltProc python package will establish the fuel composition dynamics capabilities necessary for fuel composition depletion in the context of online reprocessing. Toward the second component, a point kinetics model implementation in PyRK, and a more sophisticated advection model implementation in Moltres will be discussed. Finally, incorporation in Moltres of neutron diffusion and precursor equations will be discussed as will their implementation using the MOOSE action system.},
	author = {Huff, Kathryn D.},
	month = feb,
	year = {2019},
}

@article{rykhlevskii_modeling_2019,
	title = {Modeling and simulation of online reprocessing in the thorium-fueled molten salt breeder reactor},
	volume = {128},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454919300350},
	doi = {10.1016/j.anucene.2019.01.030},
	abstract = {In the search for new ways to generate carbon-free, reliable base-load power, interest in advanced nuclear energy technologies, particularly Molten Salt Reactors (MSRs), has resurged with multiple new companies pursuing MSR commercialization. To further develop these MSR concepts, researchers need simulation tools for analyzing liquid-fueled MSR depletion and fuel processing. However, most contemporary nuclear reactor physics software is unable to perform high-fidelity full-core depletion calculations for a reactor design with online reprocessing. This paper introduces a Python package, SaltProc, which couples with the Monte Carlo code, SERPENT2 to simulate MSR online reprocessing by modeling the changing isotopic composition of MSR fuel salt. This work demonstrates SaltProc capabilities for a full-core, high-fidelity model of the commercial Molten Salt Breeder Reactor (MSBR) concept and verifies these results to results in the literature from independent, lower-fidelity analyses.},
	urldate = {2019-01-25},
	journal = {Annals of Nuclear Energy},
	author = {Rykhlevskii, Andrei and Bae, Jin Whan and Huff, Kathryn D.},
	month = jun,
	year = {2019},
	keywords = {Simulation, Depletion, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Parallel computing, Reactor physics, Molten salt breeder reactor, Molten salt reactor, Online reprocessing, Python, Salt treatment},
	pages = {366--379},
	file = {Rykhlevskii et al. - 2019 - Modeling and simulation of online reprocessing in .pdf:/Users/huff/Zotero/storage/IQPHC25M/Rykhlevskii et al. - 2019 - Modeling and simulation of online reprocessing in .pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/W5RDKFMS/S0306454919300350.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/P6PJ667C/S0306454919300350.html:text/html},
}

@misc{rykhlevskii_simulation_2019,
	address = {Spokane, WA},
	type = {Conference},
	title = {Simulation of {Molten} {Salt} {Reactors} with {Moltres}},
	url = {https://github.com/arfc/2019-rykhl-siam},
	abstract = {The Advanced Reactors and Fuel Cycles (ARFC) group models and simulates the design, safety, and performance of advanced nuclear reactors. For these simulations coupling between physics such as neutron transport, thermal-hydraulics phenomena, and fuel performance must be taken into account. Our group performs high fidelity simulation of Gen IV reactor designs through development of models and tools for representing unique materials, complex geometries, and physical phenomena. Current work introduces an extension of the MOOSE framework, Moltres, to appropriately model coupled thermal-hydraulics and neutronics of promising liquid-fueled Molten Salt Reactor designs.

Initial simulations of the Molten Salt Reactor Experiment (MSRE) have been conducted on Blue Waters supercomputer with deterministic multiphysics. Steady state, transient, and fuel cycle analysis simulations have been run in 2D as well as 3D and compared against the Molten Salt Reactor Experiment. These simulations have occupied up to many hundreds of nodes simultaneously and have resulted in rich datasets for use in reactor design and analysis. This talk will describe how coupling between neutronics and thermal hydraulics have been established in the Moltres as well as the validation and verification efforts which have been completed.},
	author = {Rykhlevskii, Andrei},
	collaborator = {Lindsay, Alexander and Huff, Kathryn D},
	month = feb,
	year = {2019},
	file = {Rykhlevskii - 2019 - Simulation of Molten Salt Reactors with Moltres.pdf:/Users/huff/Zotero/storage/6KIVNTY2/Rykhlevskii - 2019 - Simulation of Molten Salt Reactors with Moltres.pdf:application/pdf},
}

@misc{huff_creating_2018,
	title = {Creating a {Carbon} {Free} {Future}, {Alumni} {Spotlight}: {Kathryn} {Huff}, {Ph}.{D}.},
	shorttitle = {Alumni {Spotlight}: {Kathryn} {Huff}, {Ph}.{D}.},
	url = {http://tams.unt.edu/alumni/spotlights/kathryn-huff-phd},
	language = {English},
	urldate = {2018-09-04},
	author = {Huff, Kathryn},
	collaborator = {Holland, Miranda},
	month = aug,
	year = {2018},
	note = {media},
	file = {Kathryn Huff, Ph.D. | Texas Academy of Mathematics & Science:/Users/huff/Zotero/storage/86PFLTUC/kathryn-huff-phd.html:text/html},
}

@article{timmins_power_2018,
	title = {Power {Source}: {Nuclear} engineer {Katy} {Huff} on teaching with {IPython}, reactor theory and the future of energy},
	volume = {[InClass] Engineering},
	shorttitle = {Power {Source}},
	url = {https://illinoisalumni.org/2018/08/01/in-class-power-source/},
	abstract = {Nuclear engineer Katy Huff on teaching with IPython, reactor theory and the future of energy.},
	language = {Engilish},
	number = {Summer 2018},
	journal = {University of Illinois Alumni Magazine},
	author = {Timmins, Mary},
	collaborator = {Huff, Kathryn},
	month = aug,
	year = {2018},
	note = {media},
	pages = {13},
	file = {Timmins - 2018 - Power Source Nuclear engineer Katy Huff on teachi.pdf:/Users/huff/Zotero/storage/4DFG69KU/Timmins - 2018 - Power Source Nuclear engineer Katy Huff on teachi.pdf:application/pdf},
}

@misc{lowery_women_2015,
	title = {Women in {Data} {Science}: {Kathryn} {Huff}},
	shorttitle = {Women in {Data} {Science}},
	url = {https://cds.nyu.edu/women-data-science-kathryn-huff/},
	abstract = {As part of the Moore-Sloan Data Science Initiative{\textquoteright}s ongoing commitment to promoting diversity, we are highlighting the work of 5 exceptional women in the field of data science. The first profile in our series is on Katy Huff, a Berkeley Institute for Data Science, Moore/Sloan fellow. Nuclear power is a highly controversial topic within the {\textellipsis}},
	language = {en-US},
	urldate = {2018-07-25},
	journal = {NYU Center for Data Science},
	author = {Lowery, Jack},
	month = sep,
	year = {2015},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/WD4GLQ98/women-data-science-kathryn-huff.html:text/html},
}

@article{larsen_california_2018,
	title = {California {Faculty} {Field} {Day}},
	url = {http://www.sandia.gov/news/publications/labnews/_assets/documents/issues/2018/labnews07-06-18.pdf},
	language = {en},
	journal = {Sandia National Laboratory LabNews},
	author = {Larsen, Holly},
	month = jul,
	year = {2018},
	note = {media},
	pages = {8},
	file = {Rappe - Sandia light mixer makes 11 colors at once.pdf:/Users/huff/Zotero/storage/22V6J6WR/Rappe - Sandia light mixer makes 11 colors at once.pdf:application/pdf},
}

@article{silver_microsofts_2018,
	series = {In {Focus}},
	title = {Microsoft{\textquoteright}s purchase of {GitHub} leaves some scientists uneasy},
	volume = {558},
	copyright = {2018 Nature},
	shorttitle = {They fear the online platform will become less open, but other researchers say the buyout could make {GitHub} more useful.},
	url = {http://www.nature.com/articles/d41586-018-05426-0},
	doi = {doi: 10.1038/d41586-018-05426-0},
	abstract = {They fear the data-sharing website will become less open, but other researchers say the buyout could make GitHub more useful.},
	language = {EN},
	urldate = {2018-07-06},
	journal = {Nature},
	author = {Silver, Andrew},
	month = jun,
	year = {2018},
	note = {media},
	pages = {353},
	file = {Snapshot:/Users/huff/Zotero/storage/ZXWE55CU/d41586-018-05426-0.html:text/html},
}

@article{perkel_democratic_2016,
	series = {Toolbox},
	title = {Democratic databases: science on {GitHub}},
	volume = {538},
	issn = {0028-0836},
	shorttitle = {Democratic databases},
	url = {http://www.nature.com/news/democratic-databases-science-on-github-1.20719},
	doi = {10.1038/538127a},
	abstract = {Scientists are turning to a software{\textendash}development site to share data and code.},
	language = {en},
	number = {7623},
	urldate = {2018-07-06},
	journal = {Nature News},
	author = {Perkel, Jeffrey},
	month = oct,
	year = {2016},
	note = {media},
	pages = {127},
	file = {Snapshot:/Users/huff/Zotero/storage/GQPEKFL2/democratic-databases-science-on-github-1.html:text/html},
}

@misc{bowne-anderson_data_2018,
	address = {New York, NY, USA},
	title = {Data {Science}, {Nuclear} {Engineering} and the {Open} {Source} (with {Katy} {Huff})},
	copyright = {DataCamp},
	shorttitle = {Data science, nuclear engineering, the importance of interdisciplinary data science and the open source.},
	url = {https://www.datacamp.com/community/podcast/data-science-nuclear-engineering},
	abstract = {Nuclear engineering, data science and open source software development: where do these all intersect? To find out, join Hugo and Katy Huff, Assistant Professor in the Department of Nuclear, Plasma, an},
	language = {en},
	urldate = {2018-07-06},
	journal = {Data Framed},
	publisher = {Data Camp},
	author = {Bowne-Anderson, Hugo},
	collaborator = {Huff, Kathryn D.},
	month = mar,
	year = {2018},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/25KJVGHT/12-data-science-nuclear-engineering-and-the-open-source.html:text/html},
}

@misc{mumm_professor_2018,
	address = {Urbana, IL},
	title = {Professor {Kathryn} {Huff} on the {Possibilities} in {NPRE}},
	url = {https://www.youtube.com/watch?v=w9d_QMW1hA4},
	abstract = {Assistant Professor in Nuclear, Plasma, and Radiological Engineering talks about students in NPRE and the opportunities that the major has to offer.},
	urldate = {2018-07-06},
	publisher = {Illinois Engineering},
	author = {Mumm, Susan},
	collaborator = {{Illinois Engineering} and Huff, Kathryn D.},
	month = mar,
	year = {2018},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/PLZD3J8V/watch.html:text/html},
}

@article{tippmann_my_2014,
	series = {Toolbox: {Q}\&{A}},
	title = {My digital toolbox: {Nuclear} engineer {Katy} {Huff} on version-control systems},
	issn = {0028-0836},
	shorttitle = {My digital toolbox},
	url = {http://www.nature.com/news/my-digital-toolbox-nuclear-engineer-katy-huff-on-version-control-systems-1.16014},
	doi = {10.1038/nature.2014.16014},
	abstract = {Git and GitHub are the 'laboratory notebook of scientific computing'.},
	language = {en},
	urldate = {2018-07-06},
	journal = {Nature News},
	author = {Tippmann, Sylvia},
	month = sep,
	year = {2014},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/4QXP8EIT/my-digital-toolbox-nuclear-engineer-katy-huff-on-version-control-systems-1.html:text/html},
}

@techreport{bae_numerical_2018,
	address = {Urbana, IL},
	type = {Graduate {Report}},
	title = {Numerical {Experiments} for {Verifying} {Demand} {Driven} {Deployment} {Algorithms}},
	url = {https://github.com/arfc/ddca_numerical_exp},
	abstract = {For many fuel cycle simulations, it is currently up to the user to define a deployment scheme, or facility parameters, to make sure that there{\textquoteright}s no gap in the supply chain. Or, the same goal is achieved by setting the facility capacity to infinity, which does not reflect real-world conditions.
The Demand-Driven Cycamore Archetype project (NEUP-FY16-10512) aims to develop Cycamore demand-driven deployment capabilities. The developed algorithm, in the form of Cyclus Institution agent, deploys Facilities to meet the front-end and back-end demands of the fuel cycle.
This report describes numerical tests for non-optimizing, deterministic- optimizing and stochastic-optimizing prediction algorithms.
These prediction models are being developed by the University of South Carolina. In this report, we discuss numerical experiments for testing the non-optimizing, deterministic optimizing and stochastic optimizing meth- ods. The numerical experiments will be designed for both the once through nuclear fuel cycle and advanced fuel cycles.},
	number = {UIUC-ARFC-2018-01},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Bae, Jin Whan and Chee, Gwendolyn and Huff, Kathryn},
	month = apr,
	year = {2018},
	keywords = {arfc, report},
	pages = {0--21},
	file = {Bae et al. - 2018 - Numerical Experiments for Verifying Demand Driven .pdf:/Users/huff/Zotero/storage/5X9YWIQW/Bae et al. - 2018 - Numerical Experiments for Verifying Demand Driven .pdf:application/pdf},
}

@inproceedings{rykhlevskii_online_2017,
	address = {Washington, DC, United States},
	series = {Molten {Salt} {Processing}-{Online} {Processing} {Redox}},
	title = {Online reprocessing simulation for thorium-fueled molten salt breeder reactor},
	volume = {117},
	url = {http://epubs.ans.org/?a=41258},
	abstract = {The current paper presents a single-cell model developed using the continuous-energy Serpent 2 Monte Carlo reactor physics software. It was employed to establish a Serpent- based method for finding the equilibrium core composition and core depletion of the Molten Salt Breeder Reactor (MSBR).},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Rykhlevskii, Andrei and Lindsay, Alexander and Huff, Kathryn D.},
	month = nov,
	year = {2017},
	pages = {239--242},
	file = {msbr_reproc.pdf:/Users/huff/Zotero/storage/PASSAITQ/msbr_reproc.pdf:application/pdf},
}

@inproceedings{rykhlevskii_full-core_2017,
	address = {Washington, DC, United States},
	series = {Reactor {Physics}},
	title = {Full-core analysis of thorium-fueled {Molten} {Salt} {Breeder} {Reactor} using the {SERPENT} 2 {Monte} {Carlo} code},
	volume = {117},
	url = {http://epubs.ans.org/?a=41596},
	abstract = {We used the continuous-energy Serpent 2 Monte Carlo
particle transport code to calulate whole-core depletion in the thermal spectrum Molten Salt Breeder Reactor
(MSBR) . We then compare these results with existing MCNP6
results with a more simplified geometric model. This
neutronics model is of sufficient fidelity to inform optimization
of fuel salt composition, fuel utilization, neutron fluxes, and
spectrum evaluation. Moreover, this model will be employed
for depeletion calculations, generation of problem-oriented
homogenized nuclear data (multi-group cross sections and
diffusion constants) for deterministic reactor codes, and multiphysics
simulations.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Rykhlevskii, Andrei and Lindsay, Alexander and Huff, Kathryn D.},
	month = nov,
	year = {2017},
	pages = {1343--1346},
	file = {full-core_msbr_model.pdf:/Users/huff/Zotero/storage/3F8DA752/full-core_msbr_model.pdf:application/pdf},
}

@article{smith_journal_2018,
	title = {Journal of {Open} {Source} {Software} ({JOSS}): design and first-year review},
	volume = {4},
	issn = {2376-5992},
	shorttitle = {Journal of {Open} {Source} {Software} ({JOSS})},
	url = {https://peerj.com/articles/cs-147},
	doi = {10.7717/peerj-cs.147},
	abstract = {This article describes the motivation, design, and progress of the Journal of Open Source Software (JOSS). JOSS is a free and open-access journal that publishes articles describing research software. It has the dual goals of improving the quality of the software submitted and providing a mechanism for research software developers to receive credit. While designed to work within the current merit system of science, JOSS addresses the dearth of rewards for key contributions to science made in the form of software. JOSS publishes articles that encapsulate scholarship contained in the software itself, and its rigorous peer review targets the software components: functionality, documentation, tests, continuous integration, and the license. A JOSS article contains an abstract describing the purpose and functionality of the software, references, and a link to the software archive. The article is the entry point of a JOSS submission, which encompasses the full set of software artifacts. Submission and review proceed in the open, on GitHub. Editors, reviewers, and authors work collaboratively and openly. Unlike other journals, JOSS does not reject articles requiring major revision; while not yet accepted, articles remain visible and under review until the authors make adequate changes (or withdraw, if unable to meet requirements). Once an article is accepted, JOSS gives it a digital object identifier (DOI), deposits its metadata in Crossref, and the article can begin collecting citations on indexers like Google Scholar and other services. Authors retain copyright of their JOSS article, releasing it under a Creative Commons Attribution 4.0 International License. In its first year, starting in May 2016, JOSS published 111 articles, with more than 40 additional articles under review. JOSS is a sponsored project of the nonprofit organization NumFOCUS and is an affiliate of the Open Source Initiative (OSI).},
	language = {en},
	urldate = {2018-02-19},
	journal = {PeerJ Computer Science},
	author = {Smith, Arfon M. and Niemeyer, Kyle E. and Katz, Daniel S. and Barba, Lorena A. and Githinji, George and Gymrek, Melissa and Huff, Kathryn D. and Madan, Christopher R. and Mayes, Abigail Cabunoc and Moerman, Kevin M. and Prins, Pjotr and Ram, Karthik and Rokem, Ariel and Teal, Tracy K. and Guimera, Roman Valls and Vanderplas, Jacob T.},
	month = feb,
	year = {2018},
	pages = {e147},
	file = {Full Text PDF:/Users/huff/Zotero/storage/MCQBTVVB/Smith et al. - 2018 - Journal of Open Source Software (JOSS) design and.pdf:application/pdf;Fulltext:/Users/huff/Zotero/storage/SUEMGFP2/cs-147.html:text/html;Snapshot:/Users/huff/Zotero/storage/T7FU3G6Z/cs-147.html:text/html;Snapshot:/Users/huff/Zotero/storage/GNCWWW38/cs-147.html:text/html},
}

@techreport{bae_non-algorithmic_2017,
	address = {Urbana, IL},
	type = {Graduate {Report}},
	title = {Non-algorithmic {Capability} {Gaps} for {Cyclus} and {Cycamore} transition analyses},
	url = {https://github.com/arfc/transition-scenarios},
	abstract = {As part of NEUP-FY16-10512, fuel cycle
transition scenarios were simulated using Cyclus and existing Cycamore archetypes.

The purpose of this study
is to identify current non-algorithmic gaps in the capabilities necessary for key transition scenarios.

The gaps identified through this exercise mainly pertain to the greedy exchange model, and the manual, static parameter of fuel cycle facilities. 

The scenarios are from the Idaho National Laboratory Nuclear Fuel Cycle Evaluation and Screening Report. The transition scenarios begin with EG01 and transition to EG23, EG24, EG29, EG30,
separately.},
	number = {UIUC-ARFC-2017-02},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Bae, Jin Whan and Huff, Kathryn D.},
	month = nov,
	year = {2017},
	doi = {10.5281/zenodo.1145439},
	keywords = {arfc, report},
	pages = {0--12},
	file = {uiuc-arfc-2017-02.pdf:/Users/huff/Zotero/storage/3GFDQRRG/uiuc-arfc-2017-02.pdf:application/pdf},
}

@inproceedings{kissinger_simulating_2018,
	address = {Gainesville, FL, United States},
	title = {Simulating the {Spent} {Fuel} {Recipe} of a {Sodium}-{Cooled} {Fast} {Reactor}},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} 2018 {National} {Student} {Conference},},
	publisher = {American Nuclear Society},
	author = {Kissinger, Louis},
	month = apr,
	year = {2018},
}

@article{bae_arfc/transition-scenarios:_2018,
	series = {{GitHub}},
	title = {arfc/transition-scenarios: {Synergistic} {Spent} {Nuclear} {Fuel} {Dynamics} {Within} the {European} {Union} v2.0.0},
	doi = {10.5281/zenodo.1210302},
	abstract = {This release contains code to reproduce the plots used in the paper Synergistic Spent Nuclear Fuel Dynamics Within the European Union by Jin Whan Bae, Clifford Singer, Kathryn Huff},
	urldate = {2018-04-03},
	journal = {Zenodo},
	author = {Bae, Jin Whan and Park, Gyu Tae and Huff, Katy and Chee, Gwendolyn},
	month = mar,
	year = {2018},
	keywords = {agent-based, european union, simulation, spent nuclear fuel, Transition},
	file = {Zenodo Snapshot:/Users/huff/Zotero/storage/CENLDTVM/1210302.html:text/html},
}

@misc{chaube_i2cner:_2018,
	title = {i2cner: {Holds} software, notes, documentation, and publications related to the {ARFC} {I2CNER} project on dynamic energy systems analysis},
	copyright = {BSD-3-Clause},
	shorttitle = {i2cner},
	url = {https://github.com/arfc/i2cner},
	urldate = {2018-03-27},
	publisher = {Advanced Reactors and Fuel Cycles},
	author = {Chaube, Anshuman and Huff, Kathryn},
	month = jan,
	year = {2018},
	note = {original-date: 2017-11-22T19:29:40Z},
	keywords = {Energy, Japan, analysis, energy-analysis, i2cner},
	file = {Snapshot:/Users/huff/Zotero/storage/JAK9EALT/i2cner.html:text/html},
}

@inproceedings{ridley_introduction_2017,
	address = {Washington D.C.},
	title = {An {Introduction} to {Moltres}, an {MSR} {Multiphysics} {Code}},
	url = {http://arfc.github.io/pres/2017-10-31-moltres.pdf},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Ridley, Gavin and Lindsay, Alexander and Huff, Kathryn},
	month = oct,
	year = {2017},
}

@inproceedings{huff_numerical_2012,
	address = {Chicago, IL, United States},
	series = {Modeling and {Simulation} in the {Fuel} {Cycle}},
	title = {Numerical {Calibration} of an {Analytical} {Generic} {Nuclear} {Repository} {Heat} {Transfer} {Model}},
	volume = {106},
	url = {http://epubs.ans.org/?a=13699},
	abstract = {This work describes a benchmarking effort conducted to de- termine the accuracy of a new generic geology thermal repos- itory model relative to more traditional techniques and pro- poses a physically plausible auxillary thermal resistance com- ponent to improve their agreement.},
	language = {English},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society, La Grange Park, IL 60526, United States},
	author = {Huff, Kathryn and Bauer, Theodore H.},
	month = jun,
	year = {2012},
	pages = {260--263},
	file = {ans2012pres.pdf:/Users/huff/Zotero/storage/CX5QC6ZF/ans2012pres.pdf:application/pdf;trans_v106_n1_pp260-263.pdf:/Users/huff/Zotero/storage/ICEUPH4S/trans_v106_n1_pp260-263.pdf:application/pdf},
}

@techreport{huff_fy12_2012,
	address = {Argonne, IL, United States},
	type = {Technical {Report}},
	title = {{FY12} {Sensitivity} {Studies} {Using} the {UFD} {Clay} {Generic} {Disposal} {System} {Model}},
	shorttitle = {{ANL} {FY12} {Clay} {GDSM} {Input} {Milestone}},
	abstract = {The four Generic Disposal System Models (GDSMs) developed by the Used Fuel Disposition Campaign (UFD) campaign facilitate sensitivity analysis of the long-term post-closure performance of geologic repositories in generic media with respect to various key processes and parameters [1]. Processes and parameters expected to be influential to repository performance include the rate of waste form degradation, timing of waste package failure, and various coupled geochemical and hydrologic characteristics of the natural system including diffusion, solubility, and advection.
The results here provide an overview of the relative importance of processes and parameters that affect the long term performance attributes of clay generic disposal environments. This work is not intended to give an assessment of the performance of a specific disposal system. Rather, it is intended to generically identify properties and parameters expected to influence repository performance in generic clay geologic environments.},
	language = {English},
	number = {FCRD-USED-2012-000141},
	institution = {Argonne National Laboratory (ANL)},
	author = {Huff, Kathryn D. and Nutt, W. Mark},
	month = jul,
	year = {2012},
	pages = {1--34},
	file = {ANL FY12 Clay GDSM Input Milestone.doc:/Users/huff/Zotero/storage/QXHCSHNU/ANL FY12 Clay GDSM Input Milestone.doc:application/msword;ANL FY12 Clay GDSM Input Milestone.doc:/Users/huff/Zotero/storage/GDIMRQM6/ANL FY12 Clay GDSM Input Milestone.doc:application/msword;ANL FY12 Clay GDSM Input Milestone.pdf:/Users/huff/Zotero/storage/JNRT9QMG/ANL FY12 Clay GDSM Input Milestone.pdf:application/pdf;ANL FY12 Clay GDSM Input Milestone.pdf:/Users/huff/Zotero/storage/83WMQM9G/ANL FY12 Clay GDSM Input Milestone.pdf:application/pdf;ANL FY12 Clay GDSM Input Milestone.pdf:/Users/huff/Zotero/storage/6XUI8WQ4/ANL FY12 Clay GDSM Input Milestone.pdf:application/pdf;ANL FY12 Clay GDSM Input Milestone.pdf:/Users/huff/Zotero/storage/NGR2C6GE/ANL FY12 Clay GDSM Input Milestone.pdf:application/pdf},
}

@techreport{huff_excess_2003,
	address = {Los Alamos, NM, United States},
	title = {Excess {Single} {Event} {Effects} in the {Second} {Chip} of a {Series}},
	number = {0},
	institution = {Los Alamos National Laboratory Report},
	author = {Huff, Kathryn D.},
	month = aug,
	year = {2003},
	keywords = {KHuff},
	file = {secondchip03.pdf:/Users/huff/Zotero/storage/RGPSJ4XX/secondchip03.pdf:application/pdf},
}

@techreport{huff_digital_2004,
	address = {Los Alamos, NM, United States},
	title = {Digital filtering applications to the lead slowing-down spectrometer},
	number = {0},
	institution = {Los Alamos National Laboratory Report LA-UR-04-8757, 2004},
	author = {Huff, Kathryn D.},
	year = {2004},
	keywords = {KHuff},
	file = {digitalfilter04.pdf:/Users/huff/Zotero/storage/TAM48J33/digitalfilter04.pdf:application/pdf},
}

@techreport{andreades_technical_2014,
	address = {Berkeley, CA},
	type = {Thermal {Hydraulics} {Group}},
	title = {Technical {Description} of the `{Mark} 1' {Pebble}-{Bed}, {Fluoride}-{Salt}-{Cooled}, {High}-{Temperature} {Reactor} {Power} {Plant}},
	shorttitle = {Paper 14231},
	number = {UCBTH-14-002},
	institution = {University of California, Berkeley, Department of Nuclear Engineering},
	author = {Andreades, C. and Cisneros, A.T. and Choi, J.K. and Chong, A.Y.K and Krumwiede, David L. and Huddar, Lakshana and Huff, Kathryn D. and Laufer, M.D. and Munk, Madicken and Scarlat, Raluca O. and Seifried, Jeffrey E. and Zwiebaum, Nicolas and Greenspan, Ehud and Peterson, Per F.},
	month = sep,
	year = {2014},
	file = {andreades_technical_2014.pdf:/Users/huff/Zotero/storage/AA6RXKPM/andreades_technical_2014.pdf:application/pdf},
}

@techreport{huff_next_2010,
	title = {Next {Generation} {Fuel} {Cycle} {Simulator} {Functions} and {Requirements} {Document}},
	number = {fcrd-sysa-2010-000110},
	institution = {Idaho National Laboratory},
	author = {Huff, Kathryn and Dixon, Brent},
	month = jul,
	year = {2010},
	file = {FCS- Next Generation Fuel Cycle Simulator (FCS) Functions and Requirements.pdf:/Users/huff/Zotero/storage/AUHNJFXZ/FCS- Next Generation Fuel Cycle Simulator (FCS) Functions and Requirements.pdf:application/pdf;Google Scholar Linked Page:/Users/huff/Zotero/storage/JGDIWMHB/JGDIWMHB.pdf:application/pdf;Next Generation Fuel Cycle Simulator (FCS) Functions and Requirements.docx:/Users/huff/Zotero/storage/DN3BPEMQ/Next Generation Fuel Cycle Simulator (FCS) Functions and Requirements.docx:application/vnd.openxmlformats-officedocument.wordprocessingml.document},
}

@article{carlsen_cyclus_2014,
	title = {Cyclus v1.0.0},
	doi = {10.6084/m9.figshare.1041745},
	abstract = {Cyclus is the next-generation agent-based nuclear fuel cycle simulator, providing flexibility to users and developers through adynamic resource exchange solver and plug-in, user-developed agent framework.
The goal of Cyclus is to enable a broad spectrum of fuel cycle simulation while providing a low barrier to entry for new users and agent developers. Cyclus engages with potential module developers and encourages them to join a vibrant community in anexpanding ecosystem. Users and developers are always welcome and encouraged to use or contribute to the Cyclus project.},
	urldate = {2014-06-24},
	journal = {Figshare},
	author = {Carlsen, Robert W. and Gidden, Matthew and Huff, Kathryn and Opotowsky, Arrielle C. and Rakhimov, Olzhas and Scopatz, Anthony M. and Welch, Zach and Wilson, Paul},
	month = jun,
	year = {2014},
	keywords = {Nuclear fuel cycle, agent-based simulation},
	file = {cyclus_1.0.0:/Users/huff/Zotero/storage/BDXXRM7B/Carlsen et al. - 2014 - Cyclus v1.0.0.zip:application/zip;cyclus_1.0.0:/Users/huff/Zotero/storage/HW2QA8MN/Carlsen et al. - 2014 - Cyclus v1.0.0.zip:application/zip;Figshare Download:/Users/huff/Zotero/storage/NN545PPD/Carlsen et al. - 2014 - Cyclus v1.0.0.zip:application/zip;Figshare Download:/Users/huff/Zotero/storage/5MZCI93N/Carlsen et al. - 2014 - Cyclus v1.0.0.zip:application/zip;Figshare Snapshot:/Users/huff/Zotero/storage/T982H6ZW/1041745.html:text/html;Figshare Snapshot:/Users/huff/Zotero/storage/SEA6MHKH/1041745.html:text/html;Full Text (HTML):/Users/huff/Zotero/storage/QSIAAMM8/1041745.html:text/html;Full Text (HTML):/Users/huff/Zotero/storage/H2K87S9S/1041745.html:text/html},
}

@inproceedings{krumwiede_design_2014,
	address = {Charlotte, North Carolina},
	title = {Design of the {Mark}-1 {Pebble}-{Bed}, {Fluoride}-{Salt}-{Cooled}, {High}-{Temperature} {Reactor} {Commercial} {Power} {Plant}},
	volume = {1},
	shorttitle = {Paper 14231},
	url = {https://api.semanticscholar.org/CorpusID:30717062},
	booktitle = {Proceedings of {ICAPP}},
	publisher = {American Nuclear Society},
	author = {Krumwiede, David L. and Andreades, C. and Choi, J.K. and Cisneros, A.T. and Huddar, Lakshana and Huff, Kathryn D. and Laufer, M.D. and Munk, Madicken and Scarlat, Raluca O. and Seifried, Jeffrey E. and Zwiebaum, Nicolas and Greenspan, Ehud and Peterson, Per F.},
	year = {2014},
	file = {ICAPP 2014 FHR Design.pdf:/Users/huff/Zotero/storage/BFMHUH6X/ICAPP 2014 FHR Design.pdf:application/pdf},
}

@inproceedings{gidden_agent-based_2013,
	address = {Salt Lake City, UT, United States},
	series = {Nuclear {Fuel} {Cycle} and {Fuel} {Materials}},
	title = {An {Agent}-{Based} {Framework} for {Fuel} {Cycle} {Simulation} with {Recycling}},
	volume = {45},
	url = {https://inis.iaea.org/search/search.aspx?orig_q=RN:45085433},
	abstract = {Simulation of the nuclear fuel cycle is an established field with multiple players. Prior development work has utilized tech- niques such as system dynamics to provide a solution structure for the matching of supply and demand in these simulations. In general, however, simulation infrastructure development has occured in relatively closed circles, each effort having unique considerations as to the cases which are desired to be modeled. Accordingly, individual simulators tend to have their design decisions driven by specific use cases. Presented in this work is a proposed supply and demand matching algorithm that lever- ages the techniques of the well-studied field of mathematical programming. A generic approach is achieved by treating fa- cilities as individual entities and actors in the supply-demand market which denote preferences amongst commodities. Using such a framework allows for varying levels of interaction fi- delity, ranging from low-fidelity, quick solutions to high-fidelity solutions that model individual transactions (e.g. at the fuel- assembly level). The power of the technique is that it allows such flexibility while still treating the problem in a generic man- ner, encapsulating simulation engine design decisions in such a way that future simulation requirements can be relatively easily added when needed.},
	booktitle = {Proceedings of {GLOBAL}},
	author = {Gidden, Matthew and Wilson, Paul and Huff, Kathryn D. and Carlsen, Robert W.},
	month = sep,
	year = {2013},
	file = {abstract.pdf:/Users/huff/Zotero/storage/EGDJQBFB/abstract.pdf:application/pdf;paper.pdf:/Users/huff/Zotero/storage/B5S7VPDZ/paper.pdf:application/pdf},
}

@phdthesis{huff_integrated_2011,
	address = {Madison},
	type = {Prelim},
	title = {An {Integrated} {Used} {Fuel} {Disposition} {And} {Generic} {Repository} {Model}},
	school = {University of Wisconsin},
	author = {Huff, Kathryn D.},
	month = sep,
	year = {2011},
	file = {prelim.pdf:/Users/huff/Zotero/storage/KBXHBTEV/prelim.pdf:application/pdf;prelimPres.pdf:/Users/huff/Zotero/storage/7VVNAS66/prelimPres.pdf:application/pdf},
}

@techreport{biris_analysis_2008,
	address = {Chicago, IL, United States},
	type = {capstone report},
	title = {An {Analysis} of the {Consolidated} {Fuel} {Treatment} {Center} {Nuclear} {Reprocessing} {Initiative}},
	url = {http://humanities.uchicago.edu/orgs/institute/bigproblems/Energy/BP-Energy-Reprocessing.doc},
	number = {BP-EP-2008-07},
	urldate = {2010-01-28},
	institution = {University of Chicago},
	author = {Biris, Octavia and Gracey, Kyle and Huff, Kathryn D. and Ng, Wai Keong},
	month = jun,
	year = {2008},
	keywords = {KHuff},
	file = {BP-Energy-Reprocessing.doc:/Users/huff/Zotero/storage/QHNXGMS7/BP-Energy-Reprocessing.doc:application/msword},
}

@phdthesis{huff_quiet_2008,
	address = {Chicago, IL, United States},
	type = {Undergraduate},
	title = {{QUIET} {Celestial} {Gain} {Calibrations}},
	url = {katyhuff.github.io/papers/CalibrationsThesis.pdf},
	school = {University of Chicago},
	author = {Huff, Kathryn D.},
	month = may,
	year = {2008},
	keywords = {KHuff},
	file = {Calibrations.pdf:/Users/huff/Zotero/storage/2CG34PMJ/Calibrations.pdf:application/pdf},
}

@inproceedings{scopatz_pyne:_2012,
	address = {San Diego, CA, USA},
	series = {Reactor {Physics}: {General}{\textemdash}{I}},
	title = {{PyNE}: {Python} for {Nuclear} {Engineering}},
	volume = {107},
	url = {http://epubs.ans.org/?a=14978},
	abstract = {PyNE, or 'Python for Nuclear Engineering' 1 , is a nascent
free and open source C++/Cython/Python package for perform-
ing common nuclear engineering tasks. This is intended as a
base level tool kit - akin to SciPy or Biopython - for common
algorithms in the nuclear science and engineering domain.
The remainer of this paper is composed of a discussion of the
difficulties which prevented PyNE from being written earlier,
a listing of the first cut capabilities, and a description of why
PyNE has thus far been successful and what future features are
currently planned.},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} {Winter} {Conference}},
	publisher = {American Nuclear Society},
	author = {Scopatz, Anthony and Romano, Paul K. and Wilson, Paul P. H. and Huff, Kathryn D.},
	month = nov,
	year = {2012},
	pages = {985--987},
	file = {trans_v107_n1_pp985-987.pdf:/Users/huff/Zotero/storage/TQ9E3XGC/trans_v107_n1_pp985-987.pdf:application/pdf},
}

@inproceedings{bae_benefits_2017,
	address = {Charlotte, North Carolina},
	title = {Benefits of {Siting} a {Borehole} {Repository} at a {Non}-operating {Nuclear} {Facility}},
	url = {http://epubs.ans.org/?a=43329},
	abstract = {This work evaluates a potential solution for two pressing
matters in the viability of nuclear energy: spent fuel disposal
and power plants that no longer operate. The potential benefits
of siting a borehole repository at a shut down nuclear power
plant facility are analyzed from the perspective of myriad stake-
holders. This assessment indicates that integrated siting will
make economic use of the shut down power plant, take advan-
tage of spent fuel handling infrastructure at those sites, mini-
mize transportation costs, expedite emptying the crowded spent
fuel storage pools accross the country, and will do so at sites
more likely to have consenting communities.},
	booktitle = {Proceedings of the {International} {High} {Level} {Radioactive} {Waste} {Management} {Conference}},
	publisher = {American Nuclear Society},
	author = {Bae, Jin Whan and Roy, William and Huff, Kathryn D.},
	month = apr,
	year = {2017},
	pages = {876--883},
}

@inproceedings{huff_mox_2010,
	address = {Ypsilanti, MI},
	title = {{MOX} {Fuel} {Recipe} {Approximation} {Tests} in {GENIUSv2}},
	abstract = {The GENIUS project (Global Evaluation of Nuclear Infrastructure Utilization Scenarios) was conceived as the top-level nuclear enterprise simulation tool in the Simulation Institute for Nuclear Enterprise Modelling and Analysis (SINEMA) framework1. The current version, GENIUSv2, is an object-oriented C++ application with Python-based pre- and post-processing. 
The GENIUSv2 tool proposes to inform nuclear fuel cycle technology and policy by providing a richly detailed, modular platform capable of dynamically modeling complexly integrated international fuel cycles such as those involving separations and reprocessing schemes.
Here we present results of the GENIUSv2 testing suite which demonstrate neutronics weighting methods for approximating optimal mixed oxide fuel compositions. These weighting methods achieve various levels of success at assembling critical fuel recipes from separated spent fuel streams for fuel cycles incorporating mixed oxide reprocessing. Results of neutronics constraining and neutronics weighting methods are here compared and alternative linear programmatic formulations are proposed for determining mixed-oxide (MOX) fuel compositions from available material.},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Student} {Meeting}},
	author = {Huff, Kathryn D. and Elmore, Royal A. and Oliver, Kyle M. and Wilson, Paul P.H.},
	month = apr,
	year = {2010},
	file = {ansStudent10RAP.doc:/Users/huff/Zotero/storage/V8G5DB2Z/ansStudent10RAP.doc:application/msword},
}

@inproceedings{mujica_solid-liquid-like_2008,
	title = {Solid-liquid-like transition in vibrated granular monolayers},
	url = {http://adsabs.harvard.edu/abs/2008APS..DFD.HM008M},
	abstract = {The theory of non-ideal gases in thermodynamic equilibrium, for instance the van der Waals gas model, has played a central role in the understanding of coexisting phases. Here, we report a combined experimental, numerical and theoretical study of a liquid-solid-like phase transition which takes place in a vertically vibrated fluidized granular monolayer. The first experimental setup is a long, narrow channel, with a width of the order of a few particle diameters, hence the dynamics is quasi-one-dimensional. We have considered this configuration to characterize the dynamic behavior of the phase transition. The second setup is used to measure the pressure as function of particle density in order to clarify the physical mechanism behind this phase transition. We demonstrate that the transition is mediated by waves and that it is triggered by a negative compressibility as in van der Waals phase coexistence, although the system does not satisfy the hypotheses used to understand atomic systems. Finally, in order to further characterize this phase transition, we study static and dynamic correlation functions, and bond-orientational order parameters.},
	language = {en},
	urldate = {2014-10-10},
	booktitle = {{APS} {Division} of {Fluid} {Dynamics} {Meeting} {Abstracts}},
	author = {Mujica, Nicolas and Clerc, Marcel and Cordero, Patricio and Dunstan, Jocelyn and Huff, Kathryn D. and Oyarte, Loreto and Soto, Rodrigo and Varas, German and Risso, Dino},
	month = nov,
	year = {2008},
	keywords = {KHuff},
	file = {Snapshot:/Users/huff/Zotero/storage/4GI7D9UA/2008APS..DFD.html:text/html;Solid-liquid-like transition in vibrated granular monolayers:/Users/huff/Zotero/storage/WUM5GTPK/2008APS..DFD.html:text/html},
}

@inproceedings{oliver_studying_2009,
	address = {Paris, France},
	series = {{GLOBAL} 2009: {Advanced} {Nuclear} {Fuel} {Cycles} and {Systems}},
	title = {Studying international fuel cycle robustness with the {GENIUSv2} discrete facilities/materials fuel cycle systems analysis tool},
	url = {https://sfen.fr/GLOBAL-2009},
	booktitle = {Proceedings of {GLOBAL} 2009},
	author = {Oliver, Kyle M. and Wilson, Paul P.H. and Reveillere, Arnaud and Ahn, Tae Wook and Dunn, Kerry and Huff, Kathryn D. and Elmore, Royal A.},
	month = sep,
	year = {2009},
	keywords = {Discrete Facility/ Discrete Model (DF/DM), Geniusv2, Capacity, Mass Flow Data, Nuclear Fuel Cycle Facilities, Nuclear Fuel Cycle Systems Analysis Tool},
	file = {2009_9_Oliver-GENIUS-GLOBAL2009-abstract.doc:/Users/huff/Zotero/storage/UQM8PS63/2009_9_Oliver-GENIUS-GLOBAL2009-abstract.doc:application/msword;2009_9_Oliver-GENIUS-GLOBAL2009-proceedings.pdf:/Users/huff/Zotero/storage/NUX2KS8H/2009_9_Oliver-GENIUS-GLOBAL2009-proceedings.pdf:application/pdf;2009_9_Oliver-GENIUS-GLOBAL2009-submission.doc:/Users/huff/Zotero/storage/7VZ5TN97/2009_9_Oliver-GENIUS-GLOBAL2009-submission.doc:application/msword;2009_9_Oliver-GENIUS-GLOBAL2009-submission.pdf:/Users/huff/Zotero/storage/AUWFJWRA/2009_9_Oliver-GENIUS-GLOBAL2009-submission.pdf:application/pdf},
}

@inproceedings{djokic_application_2015,
	address = {Paris, France},
	series = {{LLNL}-{CONF}-669315},
	title = {The {Application} of {CYCLUS} to {Fuel} {Cycle} {Transition} {Analysis}},
	url = {https://www.osti.gov/biblio/1241931-application-cyclus-fuel-cycle-transition-analysis},
	booktitle = {Proceedings of {Global} 2015},
	author = {Djokic, Denia and Scopatz, Anthony M. and Greenberg, Harris R. and Huff, Kathryn D. and Nibbelink, Russell P. and Fratoni, Massimiliano},
	month = sep,
	year = {2015},
	file = {5061- final.docx:/Users/huff/Zotero/storage/DC74DKEB/5061- final.docx:application/vnd.openxmlformats-officedocument.wordprocessingml.document;5061- final.pdf:/Users/huff/Zotero/storage/U9VFZXBD/U9VFZXBD.pdf:application/pdf},
}

@techreport{lindsay_advanced_2016,
	address = {Urbana, IL},
	type = {Technical {Report}},
	title = {Advanced {Reactor} {Fuel} {Cycles} {Molten} {Salt} {Reactor} {Design}},
	url = {https://github.com/arfc/MSR-design},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Lindsay, Alex and Rykhlevskii, Andrei and Huff, Kathryn},
	month = aug,
	year = {2016},
	pages = {0--17},
	file = {MSR-design.pdf:/Users/huff/Zotero/storage/VHQVZRB2/MSR-design.pdf:application/pdf},
}

@inproceedings{bates_pyne_2014,
	address = {Anaheim, CA, United States},
	title = {{PyNE} {Progress} {Report}},
	volume = {111},
	url = {http://epubs.ans.org/?a=36617},
	abstract = {PyNE is a suite of free and open source (BSD licensed)
tools to aid in computational nuclear science and engineer-
ing. PyNE seeks to provide native implementations of com-
mon nuclear algorithms, as well as an interface for the script-
ing language Python and I/O support for industry standard
nuclear codes and data formats. In the past year PyNE
has added many features including a Rigorous 2-step Ac-
tivation workflow (R2S) [1], Direct Accelerated Geometry
Monte Carlo (DAGMC) ray tracing [2], Consistent Adjoint-
Weighted Importance Sampling (CADIS) variance reduction
[3], and expanded ENSDF parsing support. As a part of our
ongoing efforts to implement a verification and validation
framework we also added continuous integration using the
Build and Test Lab [4] at the University of Wisconsin. The
PyNE development team has also improved PyNE{\textquoteright}s ease of
use by making binaries available for Windows, Mac, and
Linux through the conda package manager as well as adding
Python 3 support.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Bates, Cameron and Biondo, Elliot D. and Huff, Kathryn D. and Kiesling, Kalin and Scopatz, Anthony M.},
	month = nov,
	year = {2014},
	note = {tex.ids: bates\_pyne\_2014},
	pages = {1165--1168},
	file = {Fulltext:/Users/huff/Zotero/storage/LDIWXJRV/Bates et al. - 2014 - PyNE progress report.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/VP45CSRG/Bates et al. - 2014 - PyNE progress report.pdf:application/pdf},
}

@techreport{djokic_application_2015-1,
	title = {The {Application} of {CYCLUS} to {Fuel} {Cycle} {Transition} {Analysis}},
	url = {https://e-reports-ext.llnl.gov/pdf/791037.pdf},
	urldate = {2017-08-10},
	institution = {Lawrence Livermore National Laboratory (LLNL), Livermore, CA},
	author = {Djokic, Denia and Scopatz, Anthony and Greenberg, Harris R. and Huff, Kathryn D. and Nibbleink, R. P. and Fratoni, Massimiliano},
	month = apr,
	year = {2015},
	file = {[PDF] llnl.gov:/Users/huff/Zotero/storage/5WJ9CPM2/Djokic et al. - 2015 - The Application of CYCLUS to Fuel Cycle Transition.pdf:application/pdf},
}

@techreport{huff_benchmarking_2012,
	address = {Argonne, IL, United States},
	type = {Technical {Report}},
	title = {Benchmarking a {New} {Closed}-{Form} {Thermal} {Analysis} {Technique} {Against} a {Traditional} {Lumped} {Parameter}, {Finite}-{Difference} {Method}},
	abstract = {A benchmarking effort was conducted to determine the accuracy of a new analytic generic geology thermal repository model developed at LLNL[1, 2, 3] relative to a more traditional, numerical, lumped parameter technique.},
	language = {English},
	number = {FCRD-UFD-000142},
	institution = {Argonne National Laboratory},
	author = {Huff, Kathryn D. and Bauer, Theodore H.},
	month = jul,
	year = {2012},
	pages = {1--17},
	file = {FCRD-UFD-2012-000142.doc:/Users/huff/Zotero/storage/F662BFUK/FCRD-UFD-2012-000142.doc:application/msword;FCRD-UFD-2012-000142.pdf:/Users/huff/Zotero/storage/WZK3R2V3/FCRD-UFD-2012-000142.pdf:application/pdf},
}

@article{wilson_best_2014,
	title = {Best {Practices} for {Scientific} {Computing}},
	volume = {12},
	url = {http://dx.doi.org/10.1371/journal.pbio.1001745},
	doi = {10.1371/journal.pbio.1001745},
	abstract = {We describe a set of best practices for scientific software development, based on research and experience, that will improve scientists' productivity and the reliability of their software.},
	number = {1},
	urldate = {2014-09-08},
	journal = {PLoS Biol},
	author = {Wilson, Greg V. and Aruliah, D. A. and Brown, C. Titus and Chue Hong, Neil P. and Davis, Matt and Guy, Richard T. and Haddock, Steven H. D. and Huff, Kathryn D. and Mitchell, Ian M. and Plumbley, Mark D. and Waugh, Ben and White, Ethan P. and Wilson, Paul},
	month = jan,
	year = {2014},
	keywords = {Science, science, Computer Science - Software Engineering, Computer Science - Mathematical Software, recommendation, software},
	pages = {e1001745},
	file = {1210.0530 PDF:/Users/huff/Zotero/storage/RUGPQ89Z/Wilson et al. - 2012 - Best Practices for Scientific Computing.pdf:application/pdf;1210.0530 PDF:/Users/huff/Zotero/storage/6BWMN925/Wilson et al. - 2012 - Best Practices for Scientific Computing.pdf:application/pdf;arXiv.org Snapshot:/Users/huff/Zotero/storage/GEAQU4PR/Wilson et al. - 2012 - Best Practices for Scientific Computing.html:text/html;arXiv.org Snapshot:/Users/huff/Zotero/storage/TNJ5VZBD/Wilson et al. - 2012 - Best Practices for Scientific Computing.html:text/html;PLoS Full Text PDF:/Users/huff/Zotero/storage/JG3XZ3EN/Wilson et al. - 2014 - Best Practices for Scientific Computing.pdf:application/pdf;PLoS Full Text PDF:/Users/huff/Zotero/storage/T7PS6IGX/Wilson et al. - 2014 - Best Practices for Scientific Computing.pdf:application/pdf;PLoS Full Text PDF:/Users/huff/Zotero/storage/NZPICHHU/Wilson et al. - 2014 - Best Practices for Scientific Computing.pdf:application/pdf;PLoS Full Text PDF:/Users/huff/Zotero/storage/DRSWE54I/Wilson et al. - 2014 - Best Practices for Scientific Computing.pdf:application/pdf;PLoS Snapshot:/Users/huff/Zotero/storage/JWG3964F/infodoi10.1371journal.pbio.html:text/html;PLoS Snapshot:/Users/huff/Zotero/storage/GVVR84ZK/infodoi10.1371journal.pbio.html:text/html;PLoS Snapshot:/Users/huff/Zotero/storage/A9HDSJBB/Wilson et al. - 2014 - Best Practices for Scientific Computing.html:text/html;PLoS Snapshot:/Users/huff/Zotero/storage/FXDIXXQ2/Wilson et al. - 2014 - Best Practices for Scientific Computing.html:text/html},
}

@inproceedings{huff_dynamic_2013,
	address = {Atlanta, GA, United States},
	title = {Dynamic {Determination} of {Thermal} {Repository} {Capacity} {For} {Fuel} {Cycle} {Analysis}},
	volume = {108},
	url = {http://epubs.ans.org/?a=16524},
	abstract = {An algorithm and supporting database for rapid thermal
repository capacity calculation implemented in Cyder, a soft-
ware library for coupled thermal and hydrologic repository per-
formance analysis, is described. Integration of Cyder with the
Cyclus fuel cycle simulator is also described. Finally, a proof
of principle demonstration is presented in which the rapid cal-
culation method described here is compared with results of a
more detailed model.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Huff, Kathryn D. and Bara, Alexander T.},
	month = jun,
	year = {2013},
	pages = {123--126},
	file = {trans_v108_n1_pp123-126 (1).pdf:/Users/huff/Zotero/storage/3I456PBS/trans_v108_n1_pp123-126 (1).pdf:application/pdf},
}

@inproceedings{huff_key_2012,
	address = {San Diego, CA},
	series = {Environmental {Sciences} -- {General}},
	title = {Key {Processes} and {Parameters} in a {Generic} {Clay} {Disposal} {System} {Model}},
	volume = {107},
	url = {http://epubs.ans.org/?a=14711},
	abstract = {Sensitivity analysis was performed with respect to various
key processes and parameters affecting long-term post-closure
performance of geologic repositories in clay media. Based
on the detailed computational Clay Generic Disposal Sys-
tem Model (GDSM) developed by the Used Fuel Disposition
(UFD) campaign [1], these results provide an overview of the
relative importance of processes that affect the repository per-
formance of a generic clay disposal concept model. Further
analysis supports a basis for development of rapid abstracted
models in the context of system level fuel cycle simulation.
Processes and parameters found to influence repository perfor-
mance include the rate of waste form degradation, timing of
waste package failure, and various coupled geochemical and
hydrologic characteristics of the natural system including dif-
fusion, solubility, and advection.},
	language = {English},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Huff, Kathryn D. and Nutt, W. Mark},
	month = nov,
	year = {2012},
	pages = {208--211},
	file = {ans2012winterpres.pdf:/Users/huff/Zotero/storage/DBZTEAGJ/ans2012winterpres.pdf:application/pdf;trans_v107_n1_pp208-211.pdf:/Users/huff/Zotero/storage/SQMC825E/trans_v107_n1_pp208-211.pdf:application/pdf},
}

@inproceedings{huff_rapid_2011,
	address = {Hollywood, FL, United States},
	series = {Training, {Human} {Performance}, and {Work} {Force} {Development}},
	title = {Rapid {Peer} {Education} of a {Computational} {Nuclear} {Engineering} {Skill} {Suite}},
	volume = {104},
	url = {http://epubs.ans.org/?a=11811},
	abstract = {Detailed reactor models, massively parallelized calculations, and enormously collaborative simulation projects are increas- ingly integral to nuclear engineering. However, the quality and caliber of this work is limited by a workforce lacking formal training in a software development skill suite that is becom- ing increasingly essential. To address this unmet need, The Hacker Within (THW), a student organization at the University of Wisconsin, has developed a series of short courses address- ing best practices such as version control and test driven code development, as well as basic skills such as UNIX mobility. These 'Boot Camps' seek to provide time efficient introduc- tions to essential programming languages and tools without turning ``biochemists and mechanical engineers into computer scientists.''[1][2]},
	language = {English},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society, La Grange Park, IL 60526, United States},
	author = {Huff, Kathryn D. and Scopatz, A.M. and Preston, N.D. and Wilson, P.P.H.},
	month = jun,
	year = {2011},
	keywords = {Software, Reactor, Education, Models, Computer Science, The Hacker Within (THW)},
	pages = {103--104},
	file = {Rapid Peer Education Nuclear Engineering.pdf:/Users/huff/Zotero/storage/V438NNXC/Rapid Peer Education Nuclear Engineering.pdf:application/pdf;thwANS2011pres.pdf:/Users/huff/Zotero/storage/4CW3QC9Q/thwANS2011pres.pdf:application/pdf;trans_v104_n1_pp103-104.pdf:/Users/huff/Zotero/storage/MF3BA6DB/trans_v104_n1_pp103-104.pdf:application/pdf},
}

@inproceedings{huff_open_2011,
	address = {Hollywood, Florida},
	series = {Modeling and {Simulation} in {Fuel} {Cycle} {Separations} and {Waste} {Form} {Development}{\textemdash}{II}},
	title = {Open {Architecture} and {Modular} {Paradigm} of {Cyclus}, a {Fuel} {Cycle} {Simulation} {Code}},
	volume = {104},
	url = {http://epubs.ans.org/?a=11853},
	abstract = {The C YCLUS project at the University of Wisconsin - Madi-
son is the result of lessons learned from experience with pre-
vious nuclear fuel cycle simulation platforms. The modeling
paradigm follows the transacation of discrete quanta of ma-
terial among discrete facilities, arranged in a geographic and
institutional framework, and trading in flexible markets. Key
concepts in the design of C YCLUS include open access to the
simulation engine, modularity with regard to functionality, and
relevance to both scientific and policy analyses. The combina-
tion of modular encapsulation within the software architec-
ture and an open development paradigm allows for a bal-
ance between collaboration at multiple levels of simulation
detail and security of proprietary or sensitive data.
When comparing different nuclear fuel cycle concepts, it
can be a challenge to find any two systems analyses that com-
pare across a common set of metrics with a similar set of un-
derlying assumptions. Each analysis is likely to focus on a set
of metrics that are of interest to the team performing the analy-
sis and involve both implicit and explicit assumptions and con-
straints about the behavior of the fuel cycle system. While
a strict prescription of these metrics, assumptions and con-
straints could be proposed for comparison purposes, another
solution is to provide a systems analysis simulation tool that
provides sufficient modularity, extensibility and open access,
that it can be a basis for harmonzing to a common set. If it
becomes easier to modify an existing simulation tool to sup-
port the needs of a new analysis than it is to develop a new
tool, then it is possible that such a tool will be adopted more
universally for such analysis.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Huff, Kathryn D. and Wilson, Paul PH and Gidden, Matthew J.},
	month = jun,
	year = {2011},
	pages = {183},
	file = {cyclusANS2011pres.pdf:/Users/huff/Zotero/storage/H5VT3BKD/cyclusANS2011pres.pdf:application/pdf;trans_v104_n1_pp183-184.pdf:/Users/huff/Zotero/storage/HJPWVTI8/trans_v104_n1_pp183-184.pdf:application/pdf},
}

@inproceedings{gidden_once-through_2012,
	address = {San Diego, CA},
	series = {Nuclear {Fuel} {Cycle} {Resources}, {Sustainability}, {Reuse}, and {Recycle}},
	title = {Once-{Through} {Benchmarks} with {CYCLUS}, a {Modular}, {Open}-{Source} {Fuel} {Cycle} {Simulator}},
	volume = {107},
	url = {http://epubs.ans.org/?a=14732},
	abstract = {The C YCLUS project, based at the University of Wisconsin
- Madison, is an open source platform for exploring the long-
term impact of alternative nuclear fuel cycles. The C YCLUS
core provides the infrastructure for an agent-based approach,
allowing user-provided modules to define the behavior of fuel
cycle facilities as they interact to exchange materials. An im-
portant consequence of this approach is that innovative facility
and material exchange concepts can be introduced to a consis-
tent framework allowing for more rigorous comparison. The
C YCLUS team has recently grown and now incorporates a vari-
ety of expertise: output visualization capability through collab-
oration with the University of Utah, server-client communica-
tion via the University of Idaho, input visualization and control
with the University of Texas - Austin, and social communica-
tion expertise through collaborators at UW-Madison to assist
the mission-critical goal of relevancy vis-{\`a}-vis policy makers.
Accordingly, the C YCLUS project is expanding efforts in the
realms of both structural capability and benchmarking calcula-
tions.
A series of once-through fuel cycle scenarios are being con-
ducted using the C YCLUS core and accompanying modules.
Where needed, additional modules have been added, includ-
ing a region model that intelligently makes building decisions
given a demand function. The results of these scenarios are
then compared with VISION [1] to provide a benchmark of
the C YCLUS results.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society, La Grange Park, IL 60526, United States},
	author = {Gidden, Matthew J. and Wilson, Paul P.H. and Huff, Kathryn D. and Carlsen, Robert W.},
	month = nov,
	year = {2012},
	pages = {264--266},
	file = {trans_v107_n1_pp264-266 (1).pdf:/Users/huff/Zotero/storage/SMGXZFGK/trans_v107_n1_pp264-266 (1).pdf:application/pdf},
}

@inproceedings{elmore_geniusv2_2009,
	address = {Washington D.C., United States},
	series = {Nuclear {Fuel} {Cycle} {Codes} and {Applications}},
	title = {{GENIUSv2} {Recipe} {Approximation} {Methodology} for {Mixed}-{Oxide} {Fuel}},
	volume = {101},
	url = {http://epubs.ans.org/?a=9913},
	abstract = {The Simulation Institute for Nuclear Enterprise
Modeling and Analysis (SINEMA) developed the
GENIUS (Global Evaluation of Nuclear Infrastructure
Utilization Scenarios) project as the umbrella nuclear fuel
cycle simulation package 1 . GENIUSv2 is the next iteration
and is an object-oriented C++ program using Python pre-
and post-processing wrappers.
As a package, GENIUSv2 supports dynamic modeling
of regional and institutional interactions of nuclear fuel
cycle facilities, using a discrete material/discrete facility
paradigm. The engineering calculations and analysis
needed for each different facility and process are handled
by separate modules within GENIUSv2.
Results from the GENIUSv2 separations module are
presented that detail the robust approximation
methodology for creating mixed-oxide (MOX) fuel recipes
from available separated material.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	author = {Elmore, R. A and Oliver, K. M and Wilson, P. P.H and Ahn, Tae Wook and Dunn, Kerry L. and Huff, Kathryn D.},
	month = nov,
	year = {2009},
	keywords = {Code, Mixed-Oxide Fuel (MOX), GENIUS (Global Evaluation of Nuclear Infrastrucutre Utilization Scenarios), Nuclear Fuel Cycle Facilities, C++, Simulation Institute for Nuclear Enterprise Modeling and Analysis (SINEMA)},
	pages = {241--242},
	file = {2009_11_Elmore_ANS2009Winter_Genius.pdf:/Users/huff/Zotero/storage/SPK8GUTS/2009_11_Elmore_ANS2009Winter_Genius.pdf:application/pdf;2009_11_Elmore-ANS2009Winter_Genius.doc:/Users/huff/Zotero/storage/7G53PPN8/2009_11_Elmore-ANS2009Winter_Genius.doc:application/msword},
}

@inproceedings{huff_geniusv2_2009,
	address = {Washington D.C., United States},
	series = {Nuclear {Fuel} {Cycle} {Codes} and {Applications}},
	title = {{GENIUSv2} {Discrete} {Facilities}/{Materials} {Modeling} of {International} {Fuel} {Cycle} {Robustness}},
	volume = {101},
	url = {http://epubs.ans.org/?a=9912},
	abstract = {The GENIUS project (Global Evaluation of Nuclear
Infrastructure Utilization Scenarios) was conceived as the
top-level nuclear enterprise simulation tool in the
Simulation Institute for Nuclear Enterprise Modeling and
Analysis (SINEMA) framework 1 . The current version,
GENIUSv2, is an object-oriented C++ application with
Python-based pre- and post-processing.
The GENIUSv2 fuel cycle tool proposes to inform
nuclear fuel cycle technology and policy by providing a
richly detailed, modular platform capable of dynamically
modeling inter-regional and inter-institutional relationships
and incorporating user-defined, facility specific
technologies.
Here we present results from the GENIUSv2 testing
suite demonstrating the detailed, robust and modular nature
of its modeling capability and computational methodology.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Huff, Kathryn D. and Oliver, K. M and Wilson, P. P.H and Ahn, Tae W. and Dunn, K. and Elmore, R.},
	month = nov,
	year = {2009},
	keywords = {Geniusv2, Simulation, Code, Technology, C++, Global Evaluation of Nuclear Infrastructure Utilization Scenarios (GENIUS), Fuel cycle},
	pages = {239--240},
	file = {2009_11_Huff_ANS2009Winter_Genius.pdf:/Users/huff/Zotero/storage/2CEI63AX/2009_11_Huff_ANS2009Winter_Genius.pdf:application/pdf;2009_11_Huff-ANS2009Winter_Genius.doc:/Users/huff/Zotero/storage/BD4FSDRE/2009_11_Huff-ANS2009Winter_Genius.doc:application/msword},
}

@inproceedings{huff_hydrologic_2013,
	address = {Phoenix, AZ},
	title = {Hydrologic {Nuclide} {Transport} {Models} in {Cyder}, a {Geologic} {Disposal} {Software} {Library}.},
	shorttitle = {13328},
	url = {https://inis.iaea.org/search/search.aspx?orig_q=RN:45042278},
	booktitle = {{WM2013}},
	publisher = {Waste Management Symposium},
	author = {Huff, Kathryn D.},
	month = feb,
	year = {2013},
	file = {13328_corrected.pdf:/Users/huff/Zotero/storage/XH8F792K/13328_corrected.pdf:application/pdf;13328.pdf:/Users/huff/Zotero/storage/PDX4HEJI/13328.pdf:application/pdf},
}

@inproceedings{rochman_first_2005,
	title = {First {Measurements} with a {Lead} {Slowing}-{Down} {Spectrometer} at {LANSCE}},
	volume = {769},
	isbn = {0094-243X},
	url = {http://adsabs.harvard.edu/abs/2005AIPC..769..736R},
	doi = {10.1063/1.1945112},
	abstract = {The characteristics of a Lead Slowing-Down Spectrometer (LSDS) installed at the Los Alamos Neutron Science Center (LANSCE) are presented in this paper. This instrument is designed to study neutron-induced fission on ultra small quantities of actinides, on the order of tens of nanograms or less. The measurements of the energy-time relation, energy resolution and neutron flux are compared to simulations performed with MCNPX. Results on neutron-induced fission of 235U and
239Pu with tens of micrograms and tens of nanograms,
respectively, are presented. Finally, a digital filter designed to improve the detection of fission events at short time after the proton pulses is described.},
	urldate = {2014-10-10},
	booktitle = {Proceedings of the {International} {Conference} on {Nuclear} {Data} for {Science} and {Technology}},
	author = {Rochman, D. and Haight, R. C. and Wender, S. A. and O'Donnell, J. M. and Michaudon, A. and Huff, Kathryn D. and Vieira, D. J. and Bond, E. and Rundberg, R. S. and Kronenberg, A. and Wilhelmy, J. and Bredeweg, T. A. and Schwantes, J. and Ethvignot, T. and Granier, T. and Petit, M. and Danon, Y.},
	month = may,
	year = {2005},
	keywords = {=A, 220{\textless}, Neutron-induced fission, Nucleon-induced reactions, Spectrometers and spectroscopic techniques},
	pages = {736--739},
}

@article{andreades_design_2016,
	title = {Design {Summary} of the {Mark}-{I} {Pebble}-{Bed}, {Fluoride} {Salt}{\textendash}{Cooled}, {High}-{Temperature} {Reactor} {Commercial} {Power} {Plant}},
	volume = {195},
	issn = {00295450},
	url = {http://www.ans.org/pubs/journals/nt/a_38935},
	doi = {10.13182/NT16-2},
	abstract = {The University of California, Berkeley (UCB), has developed a preconceptual design for a commercial pebble-bed (PB), fluoride salt{\textendash}cooled, high-temperature reactor (FHR) (PB-FHR). The baseline design for this Mark-I PB-FHR (Mk1) plant is a 236-MW(thermal) reactor. The Mk1 uses a fluoride salt coolant with solid, coated-particle pebble fuel. The Mk1 design differs from earlier FHR designs because it uses a nuclear air-Brayton combined cycle designed to produce 100 MW(electric) of base-load electricity using a modified General Electric 7FB gas turbine. For peak electricity generation, the Mk1 has the ability to boost power output up to 242 MW(electric) using natural gas co-firing. The Mk1 uses direct heating of the power conversion fluid (air) with the primary coolant salt rather than using an intermediate coolant loop. By combining results from computational neutronics, thermal hydraulics, and pebble dynamics, UCB has developed a detailed design of the annular core and other key functional features. Both an active normal shutdown cooling system and a passive, natural-circulation-driven emergency decay heat removal system are included. Computational models of the FHR-validated using experimental data from the literature and from scaled thermal-hydraulic facilities-have led to a set of design criteria and system requirements for the Mk1 to operate safely and reliably. Three-dimensional, computer-aided-design models derived from the Mk1 design criteria are presented.},
	number = {3},
	urldate = {2016-09-09},
	journal = {Nuclear Technology},
	author = {Andreades, Charalampos and Cisneros, Anselmo T. and Choi, Jae Keun and Chong, Alexandre YK and Fratoni, Massimiliano and Hong, Sea and Huddar, Lakshana R. and Huff, Kathryn D. and Kendrick, James and Krumwiede, David L. and Laufer, Michael and Munk, Madicken and Scarlat, Raluca O. and Wang, Xin and Zwiebaum, Nicolas and Greenspan, Ehud and Peterson, Per},
	month = sep,
	year = {2016},
	pages = {222--238},
	file = {Snapshot:/Users/huff/Zotero/storage/C3TI9AHZ/a_38935.html:text/html;Snapshot:/Users/huff/Zotero/storage/BQ6TP5U7/a_38935.html:text/html},
}

@article{clerc_liquid-solid-like_2008,
	title = {Liquid-solid-like transition in quasi-one-dimensional driven granular media},
	volume = {4},
	issn = {1745-2473},
	url = {http://dx.doi.org.ezproxy.library.wisc.edu/10.1038/nphys884},
	doi = {10.1038/nphys884},
	abstract = {The theory of non-ideal gases at thermodynamic equilibrium, for instance the van der Waals gas model, has played a central role in our
understanding of coexisting phases, as well as the transitions between them. In contrast, the theory fails with granular matter because
collisions between the grains dissipate energy, and their macroscopic size renders thermal fluctuations negligible. When a mass of
grains is subjected to mechanical vibration, it can make a transition to a fluid state. In this state, granular matter exhibits patterns and
instabilities that resemble those of molecular fluids. Here, we report a granular solid{\textendash}liquid phase transition in a vibrating granular
monolayer. Unexpectedly, the transition is mediated by waves and is triggered by a negative compressibility, as for van der Waals
phase coexistence, although the system does not satisfy the hypotheses used to understand atomic systems. The dynamic behaviour
that we observe{\textemdash}coalescence, coagulation and wave propagation{\textemdash}is common to a wide class of phase transitions. We have combined
experimental, numerical and theoretical studies to build a theoretical framework for this transition.},
	number = {3},
	urldate = {2010-09-18},
	journal = {Nature Physics},
	author = {Clerc, M. G. and Cordero, P. and Dunstan, J. and Huff, Kathryn D. and Mujica, N. and Risso, D. and Varas, G.},
	month = mar,
	year = {2008},
	keywords = {KHuff},
	pages = {249--254},
	file = {Full Text:/Users/huff/Zotero/storage/VPQINSTH/Clerc et al. - 2008 - Liquid-solid-like transition in quasi-one-dimensio.pdf:application/pdf;Nature Snapshot:/Users/huff/Zotero/storage/BW5WXVHE/nphys884.html:text/html},
}

@phdthesis{huff_integrated_2013,
	type = {{PhD} {Dissertation}},
	title = {An {Integrated} {Used} {Fuel} {Disposition} and {Generic} {Repository} {Model} for {Fuel} {Cycle} {Analysis}},
	url = {http://gradworks.umi.com/35/92/3592735.html},
	urldate = {2013-12-16},
	school = {The University of Wisconsin - Madison},
	author = {Huff, Kathryn D.},
	month = oct,
	year = {2013},
	keywords = {Geological engineering, Kathryn D., Nuclear Physics An Integrated Used Fuel Disposition and Generic Repository Model for Fuel Cycle Analysis THE UNIVERSITY OF WISCONSIN - MADISON Paul P.H. Wilson Huff, nuclear engineering},
	file = {huff_integrated_2013.pdf:/Users/huff/Zotero/storage/BRGVKRH8/BRGVKRH8.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/9ZCVD3E3/3592735.html:text/html},
}

@techreport{huff_coupled_2017,
	type = {Blue {Waters} {Annual} {Report}},
	title = {Coupled {Multi}-{Physics} of {Advanced} {Molten} {Salt} {Nuclear} {Reactors}},
	url = {https://bluewaters.ncsa.illinois.edu/apps/docs/BW_AR_2017_linked.pdf},
	abstract = {The Advanced Reactors and Fuel Cycles Group (ARFC) conducts
modeling and simulation in the context of nuclear reactors and
fuel cycles and toward the improved safety and sustainability of
nuclear power. In the context of high-performance computing, this
work requires the coupling of multiple physics models at multiple
scales to model and simulate the design, safety, and performance
of advanced nuclear reactors. In particular, thermal{\textendash}hydraulic
phenomena, neutron transport, and fuel performance couple
tightly in nuclear reactors. Detailed spatially and temporally
resolved neutron flux and temperature distributions can improve
designs, help characterize performance, inform reactor safety
margins, and enable validation of numerical modeling techniques
for those unique physics. In the work presented here, conducted
on Blue Waters, ARFC has demonstrated the capability to simulate
coupled, transient neutronics and thermal hydraulics in an
advanced, molten-salt-fueled nuclear reactor.},
	urldate = {2018-01-23},
	institution = {National Center for Supercomputing Applications},
	author = {Huff, Kathryn and Lindsay, Alexander},
	year = {2017},
	pages = {136--137},
	file = {2017_annual_report.pdf:/Users/huff/Zotero/storage/NFINDBPD/2017_annual_report.pdf:application/pdf;Blue Waters User Portal | Annual Report:/Users/huff/Zotero/storage/HQZWV32L/annual-report.html:text/html},
}

@article{lindsay_arfc/moltres:_2017,
	title = {arfc/moltres: {Initial} {Moltres} release},
	shorttitle = {arfc/moltres},
	doi = {10.5281/zenodo.801823},
	abstract = {Functionality included in the initial Moltres release is fully-coupled simulation of multi-group neutrons, temperature, and drifting precursors in 2D-axisymmetric models of Molten Salt Reactors. Kernels and boundary conditions are dimension agnostic and can be run for 1, 2, and 3 dimensions. However, computationally efficient simulation of 3D geometries has yet to be demonstrated.},
	journal = {Zenodo},
	author = {Lindsay, Alex and Huff, Kathryn and Rykhlevskii, Andrei},
	month = jun,
	year = {2017},
}

@incollection{huff_lessons_2017,
	address = {University of California, Berkeley},
	edition = {1},
	title = {Lessons {Learned}},
	volume = {1},
	isbn = {978-0-520-29475-2},
	url = {https://www.ucpress.edu/book.php?isbn=9780520294752},
	abstract = {The Practice of Reproducible Research presents concrete examples of how researchers in the data-intensive sciences are working to improve the reproducibility of their research projects. In each of the thirty-one case studies in this volume, the author or team describes the workflow that they used to complete a real-world research project. Authors highlight how they utilized particular tools, ideas, and practices to support reproducibility, emphasizing the very practical how, rather than the why or what, of conducting reproducible research.
 
Part 1 provides an accessible introduction to reproducible research, a basic reproducible research project template, and a synthesis of lessons learned from across the thirty-one case studies. Parts 2 and 3 focus on the case studies themselves. The Practice of Reproducible Research is an invaluable resource for students and researchers who wish to better understand the practice of data-intensive sciences and learn how to make their own research more reproducible.},
	booktitle = {The {Practice} of {Reproducible} {Research}: {Case} {Studies} and {Lessons} from the {Data}-{Intensive} {Sciences}},
	publisher = {University of California Press},
	author = {Huff, Kathryn},
	editor = {Kitzes, Justin and Imamoglu, Fatma and Turek, Daniel},
	year = {2017},
}

@incollection{huff_case_2017,
	address = {University of California, Berkeley},
	edition = {1},
	title = {Case {Study}: {Cyclus} {Project}},
	volume = {1},
	isbn = {978-0-520-29475-2},
	url = {https://www.ucpress.edu/book.php?isbn=9780520294752},
	abstract = {The Practice of Reproducible Research presents concrete examples of how researchers in the data-intensive sciences are working to improve the reproducibility of their research projects. In each of the thirty-one case studies in this volume, the author or team describes the workflow that they used to complete a real-world research project. Authors highlight how they utilized particular tools, ideas, and practices to support reproducibility, emphasizing the very practical how, rather than the why or what, of conducting reproducible research.
 
Part 1 provides an accessible introduction to reproducible research, a basic reproducible research project template, and a synthesis of lessons learned from across the thirty-one case studies. Parts 2 and 3 focus on the case studies themselves. The Practice of Reproducible Research is an invaluable resource for students and researchers who wish to better understand the practice of data-intensive sciences and learn how to make their own research more reproducible.},
	booktitle = {The {Practice} of {Reproducible} {Research}: {Case} {Studies} and {Lessons} from the {Data}-{Intensive} {Sciences}},
	publisher = {University of California Press},
	author = {Huff, Kathryn},
	editor = {Kitzes, Justin and Imamoglu, Fatma and Turek, Daniel},
	year = {2017},
}

@inproceedings{westphal_signatures_2018,
	address = {Raleigh, N.C.},
	title = {Signatures and {Observables} in the {Nuclear} {Fuel} {Cycle}},
	booktitle = {{CNEC} {Annual} {Workshop}},
	publisher = {North Carolina State University},
	author = {Westphal, Gregory and Huff, Kathryn D.},
	month = feb,
	year = {2018},
	note = {(Poster)},
}

@article{allen_engineering_2017,
	title = {Engineering {Academic} {Software} ({Dagstuhl} {Perspectives} {Workshop} 16252)},
	volume = {6},
	issn = {2193-2433},
	url = {http://drops.dagstuhl.de/opus/volltexte/2017/7146},
	doi = {10.4230/DagMan.6.1.1},
	abstract = {Software is often a critical component of scientific research. It can be a component of the academic research methods used to produce research results, or it may itself be an academic research result. Software, however, has rarely been considered to be a citable artifact in its own right. With the advent of open-source software, artifact evaluation committees of conferences, and journals that include source code and running systems as part of the published artifacts, we foresee that software will increasingly be recognized as part of the academic process. The quality and sustainability of this software must be accounted for, both a priori and a posteriori.

The Dagstuhl Perspectives Workshop on {\textquotedblleft}Engineering Academic Software{\textquotedblright} has examined the strengths, weaknesses, risks, and opportunities of academic software engineering. A key outcome of the workshop is this Dagstuhl Manifesto, serving as a roadmap towards future professional software engineering for software-based research instruments and other software produced and used in an academic context. The manifesto is expressed in terms of a series of actionable {\textquotedblleft}pledges{\textquotedblright} that users and developers of academic research software can take as concrete steps towards improving the environment in which that software is produced.},
	number = {1},
	journal = {Dagstuhl Manifestos},
	author = {Allen, Alice and Aragon, Cecilia and Becker, Christoph and Carver, Jeffrey and Chis, Andrei and Combemale, Benoit and Croucher, Mike and Crowston, Kevin and Garijo, Daniel and Gehani, Ashish and Goble, Carole and Haines, Robert and Hirschfeld, Robert and Howison, James and Huff, Kathryn and Jay, Caroline and Katz, Daniel S. and Kirchner, Claude and Kuksenok, Katie and L{\"a}mmel, Ralf and Nierstrasz, Oscar and Turk, Matt and Nieuwpoort, Rob van and Vaughn, Matthew and Vinju, Jurgen J.},
	editor = {al, Alice Allen et},
	year = {2017},
	keywords = {Academic software, Research software, Software citation, Software sustainability},
	pages = {1--20},
	annote = {Keywords: Academic software, Research software, Software citation, Software sustainability},
	file = {Full Text PDF:/Users/huff/Zotero/storage/AP6TACTU/Allen et al. - 2017 - Engineering Academic Software (Dagstuhl Perspectiv.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/VCZFTX9V/7146.html:text/html},
}

@techreport{ridley_multiphysics_2017,
	address = {Urbana, IL},
	type = {Undergraduate {Report}},
	title = {Multiphysics {Analysis} of {Molten} {Salt} {Reactor} {Transients}},
	url = {https://github.com/arfc/publications/tree/2017-ridley-msrTransients},
	abstract = {Molten salt nuclear reactor technology has not yet been constructed for industrial scale. High fidelity simulation capability of both transients and steady-state behavior must be developed for reactor licensing. The simulations should make use of high performance computing (HPC) in order
to come to realistic results while minimizing assumptions. High resolution simulation of limiting reactor transients using
open-source software can inform reproducible results suitable for preliminary licensing activity. We present example results of the new code.},
	number = {UIUC-ARFC-2017-01},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Ridley, Gavin and Lindsay, Alexander and Turk, Matthew and Huff, Kathryn},
	month = aug,
	year = {2017},
	note = {DOI 10.5281/zenodo.1145437},
	keywords = {arfc, report},
	pages = {0--12},
	file = {uiuc-arfc-2017-01.pdf:/Users/huff/Zotero/storage/ASUYNNXT/uiuc-arfc-2017-01.pdf:application/pdf},
}

@article{lindsay_moltres_2018,
	title = {Moltres: finite element based simulation of molten salt reactors},
	volume = {3},
	shorttitle = {Moltres},
	doi = {10.21105/joss.00298},
	abstract = {Moltres is a physics application for multiphysics modeling of fluid-fueled molten salt reactors
(MSRs) (Lindsay et al. 2018). It couples equations for neutron diffusion, thermal
hydraulics, and delayed neutron precursor transport. Neutron diffusion and precursor
transport equations are set-up using an action system that allows the user to use an arbitrary
number of neutron energy and precursor groups respectively with minimal input
changes. Moltres sits on top of the Multi-physics Object-Oriented Simulation Environment
(Gaston et al. 2015) and hence uses the finite element method to discretize the
governing partial differential equations. In general the resulting system of non-linear algebraic
equations is linearized using the Newton-Raphson method and then solved using
the Portable, Extensible Toolkit for Scientific Computation (Balay et al. 2017). Assembly
of the Jacobian and residual, and the linear solve are parallelized using MPI which
allows Moltres to be run in massively parallel environments. Runs on the Blue Waters
supercomputer at Illinois have utilized up to 608 cores.
Moltres and MOOSE allow use of different basis functions for different system variables.
Because of the purely diffusive nature of the neutron diffusion equations, neutron fluxes are
typically discretized using continuous first-degree Lagrange polynomials and the degrees of
freedom are associated with mesh nodes. The temperature variable may also be discretized
with a continuous Lagrange basis, or a discontinuous basis of arbitrary degree monomials
may be employed depending on the relative balance of heat convection to conduction. The
purely hyperbolic precursor transport is currently discretized using constant monomials,
which is equivalent to a first-order finite volume discretization. Moltres supports both
segregated (through Picard iteration) and monolithic solutions of the equation system.
However, due to the feedback between the power spectrum and temperature dependence
of macroscopic cross-sections, monolithic solves have demonstrated superior robustness
with segregated techniques often unable to converge to a solution. This result emphasizes
the importance of a fully coupled multi-physics framework like the one that Moltres and
MOOSE provide and suggests that iteratively coupling codes devoted to single physics
(K{\'o}ph{\'a}zi, Lathouwers, and Kloosterman 2009) may result in limited flexibility.},
	number = {21},
	urldate = {2018-01-08},
	journal = {The Journal of Open Source Software},
	author = {Lindsay, Alexander and Huff, Kathryn},
	month = jan,
	year = {2018},
	pages = {1--2},
	file = {Full Text PDF:/Users/huff/Zotero/storage/MJIZZW4P/Lindsay and Huff - 2018 - Moltres finite element based simulation of molten.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/E3ARQ46H/joss.html:text/html},
}

@inproceedings{smith_journal_2017,
	address = {Atlanta, GA},
	title = {The {Journal} of {Open} {Source} {Software}},
	volume = {Computational Science and Engineering},
	url = {https://figshare.com/articles/The_Journal_of_Open_Source_Software/4688911},
	doi = {10.6084/m9.figshare.4688911.v1},
	abstract = {Poster presented at SIAM CSE17 PP108 Minisymposterium: Software Productivity and Sustainability for CSE and Data ScienceAbstract:This poster describes the motivation and progress of the Journal of Open Source Software (JOSS), a free, open-access journal designed to publish brief papers about research software. The primary purpose of JOSS is to enable developers of research software to receive citation credit equivalent to typical archival publications. JOSS papers are deliberately extremely short, and are required to include a short abstract describing the purpose and functionality of the software, authors and their affiliations, and key references, as well as link to an archived version of the software (e.g., DOI obtained from Zenodo). Upon acceptance, papers receive a CrossRef DOI. Rather than a review of a lengthy software paper (including, e.g., methodology, validation, sample results), JOSS submissions undergo rigorous peer review of both the abstract and software itself, including documentation, tests, continuous integration, and licensing. The JOSS review process is modeled on the established approach of the rOpenSci collaboration. The entire submission and review process occurs openly on GitHub; papers not yet accepted remain visible and under review until the authors make appropriate changes for acceptance---unlike other journals, papers requiring major revision are not rejected. Since its public release in May 2016, JOSS has published 26 accepted papers as of September 2016, with an additional 20 submitted and under review.},
	urldate = {2018-07-22},
	booktitle = {Poster},
	publisher = {Society for Industrial and Applied Mathematics},
	author = {Smith, Arfon and Barba, Lorena A. and Githinji, George and Gymrek, Melissa and Huff, Kathryn and Katz, Daniel S. and Madan, Christopher and Mayes, Abigail Cabunoc and Moerman, Kevin M. and Niemeyer, Kyle and Prins, Pjotr and Ram, Karthik and Rokem, Ariel and Teal, Tracy and Vanderplas, Jake},
	month = feb,
	year = {2017},
	keywords = {Software citation, JOSS, Open research software, Open software, SIAM-CSE17-PP108},
	file = {Figshare Snapshot:/Users/huff/Zotero/storage/36AQBT45/4688911.pdf:application/pdf},
}

@misc{kamuda_comparison_2018,
	address = {Ann Arbor, MI},
	type = {Poster},
	title = {A {Comparison} of {Machine} {Learning} {Methods} for {Automated} {Gamma}-{Ray} {Spectroscopy}},
	url = {http://arfc.github.io/pres/2018-06-13-SORMA.pdf},
	abstract = {Pattern recognition algorithms such as artificial neural networks (ANNs) and convolution neural networks (CNNs) are prime candidates to perform automated gamma-ray spectroscopy. The way these models train and operate mimic how trained spectroscopists identify gamma-ray spectra. These models have shown promise in identifying gamma-ray spectra with large calibration drift and unknown background radiation fields. In this work, machine learning algorithms including ANNs and CNNs will be applied to gamma-ray spectroscopy with NaI detectors. The performance of these algorithms will be compared using a set of simulated gamma-ray spectra. This work has the potential to advance the NNSA{\textquoteright}s nonproliferation mission by creating advanced handheld radiation detectors.},
	author = {Kamuda, Mark},
	collaborator = {Huff, Kathryn},
	month = jun,
	year = {2018},
}

@misc{huff_modeling_2018,
	address = {Ann Arbor, MI},
	type = {Invited {Seminar}},
	title = {Modeling and {Simulation} at {Disparate} {Scales}: {Molten} {Salt} {Reactor} {Physics} and {International} {Fuel} {Cycle} {Transitions}},
	url = {https://katyhuff.github.io/2018-02-16-ners/},
	abstract = {The world's energy future depends on improved safety and sustainability of nuclear reactor designs and fuel cycle strategies. Insights can be drawn from numerical experiments that model and simulate these systems. Both reactor and nuclear fuel cycle dynamics are sufficiently complex that sophisticated scientific software methods and high-performance computing resources are essential to understanding them. Furthermore, improved reproducibility and verification in these numerical experiments can be achieved through judicious use of scientific computing best practices. Using examples drawn from spent nuclear fuel management and advanced reactor design, this talk will describe the role and benefits of modeling and simulation combining insights from multiple scales in nuclear engineering challenges. The talk will introduce Moltres, a new physics application for multiphysics modeling of liquid-fueled molten salt reactors. The neutronics model, thermal hydraulics model, and their coupling in the MOOSE framework will be described. Results for many-channel configurations in 2D-axisymmetric and 3D coordinates will be presented and compared against other coupled models as well as the Molten Salt Reactor Experiment. This talk will also touch on isotope identification with neural networks and recent transition analyses using Cyclus, an agent-based nuclear fuel cycle simulation framework.},
	author = {Huff, Kathryn D.},
	month = feb,
	year = {2018},
}

@misc{rykhlevskii_computational_2018,
	address = {Sun River, OR},
	type = {Symposium},
	title = {Computational {Tools} for {Molten} {Salt} {Reactor} {Simulation}},
	url = {http://arfc.github.io/pres/2018-04-07-comp-tools-msr.pdf},
	abstract = {The Advanced Reactors and Fuel Cycles (ARFC) group models and simulates the design, safety, and performance of advanced nuclear reactors. Such reactors involve tight coupling between physics such as thermal-hydraulic phenomena, neutron transport, and fuel performance. Current work introduces an extension of the MOOSE framework, Moltres, to appropriately model coupled thermal-hydraulics and neutronics of promising molten-salt-fueled reactor designs. Additionally, we have developed an online reprocessing simulation tool, SaltProc which includes fission product removal, fissile material separations, and refuelling for time dependent analysis of fuel-salt evolution. Initial simulations of the Molten Salt Reactor Experiment and the conceptual Molten Salt Breeder Reactor have been conducted on Blue Waters with deterministic multiphysics and Monte Carlo methods respectively. Steady state, transient, and fuel cycle analysis simulations have been run in 2D as well as 3D and compared against the Molten Salt Reactor Experiment. Fuel cycle dynamics and quasi-equilibrium compositions were obtained from depletion and reprocessing simulations for a 20-year time frame. The MSBR full-core safety analysis was performed at the startup and equilibrium fuel salt compositions, for important reactor safety parameters. In this work, conducted on Blue Waters, ARFC has demonstrated the capability to model complex physics in an advanced molten-salt-fueled nuclear reactor.},
	author = {Rykhlevskii, Andrei},
	collaborator = {Huff, Kathryn D.},
	month = jun,
	year = {2018},
}

@inproceedings{chaube_dynamic_2018,
	address = {Fukuoka, Japan},
	title = {Dynamic {Transition} {Analysis} with {TIMES}},
	booktitle = {{I2CNER} {Annual} {Symposium}},
	publisher = {Kyushu University},
	author = {Chaube, Anshuman and Stubbins, James and Huff, Kathryn D.},
	month = jan,
	year = {2018},
	note = {(Poster)},
	file = {poster.pdf:/Users/huff/Zotero/storage/VL5BDNQB/poster.pdf:application/pdf},
}

@misc{huff_reducing_2017,
	address = {Grainger Library, Urbana, IL},
	type = {Lightning {Symposium}},
	title = {Reducing {Classroom} {Bias} with a {Random} {Name} {Picker}},
	url = {arfc.github.io/pres/2017-03-02-ae3.pdf},
	language = {en},
	author = {Huff, Kathryn D.},
	month = mar,
	year = {2017},
	note = {https://mediaspace.illinois.edu/media/1\_e7goeiyo},
	file = {Huff - 2017 - Reducing Classroom Bias with a Random Name Picker.pdf:/Users/huff/Zotero/storage/PWPEHPMF/Huff - 2017 - Reducing Classroom Bias with a Random Name Picker.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/ZFTAABLX/1_e7goeiyo.html:text/html},
}

@article{bae_standardized_2019,
	title = {Standardized verification of the {Cyclus} fuel cycle simulator},
	volume = {128},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454919300179},
	doi = {10.1016/j.anucene.2019.01.014},
	abstract = {Many nuclear fuel cycle simulators can analyze transitions from once-through to advanced nuclear fuel cycles. Verification studies compare various fuel cycle analysis tools to test agreement and identify sources of difference. A recent verification study, Feng et al. (2016) established transition scenario test case specifications and accordingly evaluated national laboratory nuclear fuel cycle simulators, DYMOND, VISION, ORION, and MARKAL. This work verifies the performance of Cyclus, the agent-based, open-source fuel cycle simulator, using the test case specifications in Feng et. al. In this work, Cyclus demonstrates agreement with the results from the previous verification study. Minor differences reflect intentional, detailed material tracking in the Cycamore reactor module. These results extend the example results in Feng et al. to further enable future verification of additional nuclear fuel cycle simulation tools.},
	urldate = {2019-01-25},
	journal = {Annals of Nuclear Energy},
	author = {Bae, Jin Whan and Peterson-Droogh, Joshua L. and Huff, Kathryn D.},
	month = jun,
	year = {2019},
	keywords = {Simulation, Verification, Nuclear fuel cycle, repository, agent based modeling, Object orientation, Systems analysis, Finite elements, Hydrologic contaminant transport, MOOSE, Multiphysics, nuclear engineering, Parallel computing, Reactor physics, C},
	pages = {288--291},
	file = {Bae et al. - 2018 - Standardized Verification of the Cyclus Fuel Cycle.pdf:/Users/huff/Zotero/storage/T6Q5G2AW/Bae et al. - 2018 - Standardized Verification of the Cyclus Fuel Cycle.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/UXQWH3GA/UXQWH3GA.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/WFFQBL3B/S0306454919300179.html:text/html},
}

@inproceedings{wang_coupled_2016,
	address = {Charlotte, North Carolina},
	title = {Coupled {Reactor} {Kinetics} and {Heat} {Transfer} {Model} for {Fluoride} {Salt}-{Cooled} {High}-{Temperature} {Reactor} {Transient} {Analysis}},
	url = {http://dx.doi.org/10.1115/ICONE24-60728},
	doi = {10.1115/ICONE24-60728},
	abstract = {Coupled reactor kinetics and heat transfer models have been developed at the University of California, Berkeley (UCB) to study Pebble-Bed, Fluoride-salt-cooled, High-temperature Reactors (PB-FHRs) transient behaviors. This paper discusses a coupled point kinetics model and a two-dimensional diffusion model. The former is based on the point kinetics equations with six groups of delayed neutrons and the lumped capacitance heat transfer equations. To account for the reflector effect on neutron lifetime, additional (fictional) groups of delayed neutrons are added in the point kinetics equations to represent the thermalized neutrons coming back from the reflectors. The latter is based on coupled multi-group neutron diffusion and finite element heat transfer model. Multi-group cross sections and diffusion coefficients are generated using the Monte Carlo code Serpent and defined as input in COMSOL 5.0.},
	urldate = {2016-11-17},
	booktitle = {Proceedings of {ICONE} 2016},
	author = {Wang, Xin and Huff, Kathryn D. and Aufiero, Manuele and Peterson, Per F. and Fratoni, Massimiliano},
	month = jun,
	year = {2016},
	note = {JC0003},
	file = {Full Text PDF:/Users/huff/Zotero/storage/WJJ2NXBT/Wang et al. - 2016 - Coupled Reactor Kinetics and Heat Transfer Model f.pdf:application/pdf;ICONE_paper.docx:/Users/huff/Zotero/storage/AS8LABIN/ICONE_paper.docx:application/vnd.openxmlformats-officedocument.wordprocessingml.document;ICONE_paper.pdf:/Users/huff/Zotero/storage/G33RQ4JZ/ICONE_paper.pdf:application/pdf},
}

@inproceedings{wang_sensitivity_2016,
	address = {San Francisco, CA},
	title = {A {Sensitivity} {Study} of a {Coupled} {Kinetics} and {Thermal}-{Hydraulics} {Model} for {Fluoride}-{Salt}-{Cooled}, {High}-{Temperature} {Reactor} ({FHR}) {Transient} {Analysis}},
	url = {icapp.ans.org},
	booktitle = {Proceedings of {ICAPP} 2016},
	publisher = {International Congress on Advances in Nuclear Power Plants},
	author = {Wang, Xin and Huff, Kathryn D. and Aufiero, Manuele and Peterson, Per F. and Fratoni, Massimiliano},
	month = apr,
	year = {2016},
	pages = {Paper 16555},
}

@inproceedings{kamuda_comparison_2018-1,
	address = {Ann Arbor, MI},
	title = {A {Comparison} of {Machine} {Learning} {Methods} for {Automated} {Gamma}-{Ray} {Spectroscopy}},
	url = {http://arfc.github.io/pres/2018-06-13-SORMA.pdf},
	abstract = {This poster outlines progress made comparing fully connected neural networks and convolution neural networks for isotope quantification in NaI gamma-ray spectra.},
	booktitle = {Proceedings of {SORMA2018}},
	author = {Kamuda, Mark and Zhao, Jifu and Huff, Kathryn},
	month = jun,
	year = {2018},
}

@misc{huff_neutron_2018,
	address = {Mumbai, India},
	type = {Invited {Talk}},
	title = {Neutron {Kinetics} in {Liquid}-{Fueled} {Nuclear} {Reactors}},
	url = {https://katyhuff.github.io/2018-12-18-mumbai},
	abstract = {Modeling and simulation of neutron kinetics in liquid-fueled nuclear reactors incorporates three major challenging components. First, it is necessary to establish the dynamic evolution of fuel composition via depletion and online reprocessing. Additionally, multiphysics analysis of the thermal hydraulics and neutronics in such a reactor must incorporate thermal feedbacks and material expansion feedbacks. Finally, drift of delayed neutron precursors must be incorporated into the kinetics analysis due to the mobility of the liquid fuel. This talk will discuss all three components. Toward the first component, a discussion of the SaltProc python package will establish the fuel composition dynamics capabilities necessary for fuel composition depletion in the context of online reprocessing. Toward the second component, a point kinetics model implementation in PyRK, and a more sophisticated advection model implementation in Moltres will be discussed. Finally, incorporation in Moltres of neutron diffusion and precursor equations will be discussed as will their implementation using the MOOSE action system.},
	author = {Huff, Kathryn D.},
	month = dec,
	year = {2018},
}

@misc{bae_impact_2018,
	address = {Orlando, FL},
	type = {Poster},
	title = {Impact of {Composition} {Approximation} on {Simulated} {Nuclear} {Fuel} {Cycle} {Metrics}},
	url = {http://arfc.npre.illinois.edu/pres/2018-11-13-bae-answinter2018.pdf},
	author = {Bae, Jin Whan and Joshua, Peterson-Droogh and Huff, Kathryn D.},
	month = nov,
	year = {2018},
}

@inproceedings{westphal_pyre_2018,
	address = {Orlando, FL},
	title = {{PyRe}: {A} {Cyclus} {Pyroprocessing} {Facility} {Archetype}},
	url = {http://epubs.ans.org/?a=44666},
	abstract = {This work assesses system parameters that influence separation efficiency and throughput of pyroprocessing facilities. We leverage these parameters to implement a customizable pyroprocessing facility archetype, PyRe, for use with the Cyclus framework. This generic facility model will allow simulations to quantify signatures and observables associated with various operational modes and material throughputs for a variety of facility designs. Such quantification can aid timely detection of material diversion. This paper describes the facility archetype design, pyroprocessing flowsheets captured by the model, and simulation capabilities it enables. To analyze data retrieved from the model, we additionally propose a class for tracking and observing signatures and observables which will be extensible for other facility archetypes in the future.},
	booktitle = {Proceedings of the 2018 {Advances} in {Nuclear} {Nonproliferation} {Technology} and {Policy} {Conference}},
	publisher = {American Nuclear Society},
	author = {Westphal, Greg and Huff, Kathryn},
	month = nov,
	year = {2018},
	pages = {73--76},
	file = {2018-westphal-antpc.pdf:/Users/huff/Zotero/storage/UDEC8I6A/2018-westphal-antpc.pdf:application/pdf},
}

@misc{huff_enabling_2018,
	address = {Charlotte, North Carolina},
	type = {Poster},
	title = {Enabling {Load}-{Following} {Capability} in the {TAP} {MSR}},
	url = {https://arpa-e.energy.gov/sites/default/files/1300%20Huff_approved.pdf},
	author = {Huff, Kathryn},
	month = dec,
	year = {2018},
}

@inproceedings{huff_extensions_2014,
	address = {Anaheim, CA, United States},
	series = {Fuel {Cycle} {Options} {Analysis} -- {III}},
	title = {Extensions to the {Cyclus} {Ecosystem} {In} {Support} of {Market}-{Driven} {Transition} {Capability}},
	url = {http://epubs.ans.org/?a=36345},
	abstract = {The C YCLUS Fuel Cycle Simulator [1] is a framework
for assessment of nuclear fuel cycle options. While C Y -
CLUS has previously been capable of system transitions
from the current fuel cycle strategy to a future option, those
transitions have never previously been driven by market
forces in the simulation. This summary describes a set
of libraries [2] that have been contibuted to the C YCLUS
framework to enable a market-driven transition analysis.
This simulation framework is incomplete without a suite
of dynamically loadable libraries representing the process
physics of the nuclear fuel cycle (i.e. mining, fuel fabri-
cation, chemical processing, transmutation, reprocessing,
etc.). Within Cycamore [3], the additional modules reposi-
tory within the C YCLUS ecosystem, provides some basic li-
braries to represent these processes. However, extension of
C YCLUS with new capabilities is community-driven, rely-
ing on contributions by user-developers. The libraries con-
tributed in this work are examples of such contributions.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Huff, Kathryn D. and Fratoni, Massimiliano and Greenberg, Harris},
	month = nov,
	year = {2014},
	note = {LLNL-PROC-656426},
	pages = {245--248},
	file = {huff_extensions_2014.pdf:/Users/huff/Zotero/storage/MV2TCELS/huff_extensions_2014.pdf:application/pdf},
}

@inproceedings{huff_pyrk:_2015,
	address = {Austin, TX, United States},
	title = {{PyRK}: {A} {Python} {Package} {For} {Nuclear} {Reactor} {Kinetics}},
	shorttitle = {{PyRK}},
	url = {http://conference.scipy.org/proceedings/scipy2015/kathryn_huff.html},
	doi = {10.25080/Majora-7b98e3ed-00d},
	abstract = {In this work, a new python package, PyRK (Python for Reactor Kinetics), is introduced. PyRK has been designed to simulate, in zero dimensions, the transient, coupled, thermal-hydraulics and neutronics of time-dependent behavior in nuclear reactors. PyRK is intended for analysis of many commonly studied transient scenarios including normal reactor startup and shutdown as well as abnormal scenarios including Beyond Design Basis Events (BDBEs) such as Accident Transients Without Scram (ATWS). For robustness, this package employs various tools within the scientific python ecosystem. For additional ease of use, it employs a reactor-agnostic, object-oriented data model, allowing nuclear engineers to rapidly prototype nuclear reactor control and safety systems in the context of their novel nuclear reactor designs.},
	urldate = {2018-11-08},
	booktitle = {Proceedings of the 14th {Python} in {Science} {Conference}},
	publisher = {SciPy},
	author = {Huff, Kathryn},
	year = {2015},
	pages = {87--93},
	file = {Full Text PDF:/Users/huff/Zotero/storage/W6JJYW6S/Huff - 2015 - PyRK A Python Package For Nuclear Reactor Kinetic.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/WN5HB4GE/kathryn_huff.html:text/html},
}

@inproceedings{chee_validation_2018,
	address = {Orlando, FL},
	title = {Validation of {Spent} {Nuclear} {Fuel} {Output} by {Cyclus}, a {Fuel} {Cycle} {Simulator} {Code}},
	volume = {119},
	shorttitle = {Fuel {Cycle} {Analysis}},
	url = {http://epubs.ans.org/?a=44198},
	abstract = {Cyclus, a nuclear fuel cycle simulator, was used to simulate the United States{\textquoteright} nuclear fuel cycle from 1967 through 2013. The spent nuclear spent nuclear fuel (SNF) inventory from the Cyclus simulation was compared to the SNF inventory from the Department of Energy (DOE) sponsored Used Nuclear Fuel Storage, Transportation \& Disposal Analysis Resource and Data System (UNFST\&DARDS) Unified Database (UDB). The UDB provides comprehensive and consistent technical data on reactor sites and SNF from the beginning of nuclear reactor operation in the United States (US) until 2013. This comparison between Cyclus and UDB establishes a realistic validation of Cyclus{\textquoteright} capability to produce total spent fuel mass and accurate isotopic compositions that closely match reality.},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} {Winter} {Meeting} 2018},
	publisher = {American Nuclear Society},
	author = {Chee, Gwendolyn and Park, Gyutae and Huff, Kathryn D.},
	month = nov,
	year = {2018},
	pages = {219--222},
	file = {Chee et al. - 2018 - Validation of Spent Nuclear Fuel Output by Cyclus,.pdf:/Users/huff/Zotero/storage/PE67YJBQ/Chee et al. - 2018 - Validation of Spent Nuclear Fuel Output by Cyclus,.pdf:application/pdf;Gwendolyn-Chee-ANSWinter2018.pdf:/Users/huff/Zotero/storage/IYYD7F3R/Gwendolyn-Chee-ANSWinter2018.pdf:application/pdf},
}

@misc{mumm_npre_2018,
	type = {University},
	title = {{NPRE} researchers to investigate load-following capabilities for molten salt reactors {\textbar} {NPRE} {Illinois}},
	url = {https://npre.illinois.edu/news/npre-researchers-investigate-load-following-capabilities-molten-salt-reactors},
	abstract = {A team of researchers from Nuclear, Plasma, and Radiological Engineering at the University of Illinois at Urbana-Champaign are examining ways to enable this load-following capability. The scientists are conducting simulations to determine how to remove unwanted fission by-products that slow reaction rates and, thus, energy production.},
	urldate = {2018-10-30},
	journal = {Nuclear, Plasma, and Radiological Engineering News},
	author = {Mumm, Susan},
	month = jun,
	year = {2018},
	note = {media},
	file = {NPRE researchers to investigate load-following capabilities for molten salt reactors | NPRE Illinois:/Users/huff/Zotero/storage/8CE8KI6V/npre-researchers-investigate-load-following-capabilities-molten-salt-reactors.html:text/html},
}

@article{letzter_when_2019,
	chapter = {Planet Earth},
	title = {When {Chernobyl} {Blew}, {They} {Dumped} {Boron} and {Sand} into the {Breach}. {What} {Would} {We} {Do} {Today}?},
	url = {https://www.livescience.com/65515-chernobyl-in-modern-times-nuclear-emergency.html},
	abstract = {In 1986, the Soviets dumped sand and boron from helicopters onto the exposed Chernobyl uranium core. How would we handle it today?},
	urldate = {2019-05-22},
	journal = {Live Science},
	author = {Letzter, Rafi},
	month = may,
	year = {2019},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/GQFHICX8/65515-chernobyl-in-modern-times-nuclear-emergency.html:text/html},
}

@misc{kugelmass_katy_2019,
	address = {Urbana, IL},
	title = {Katy {Huff}, {University} of {Illinois} on {Apple} {Podcasts}},
	shorttitle = {?{Titans} {Of} {Nuclear} {\textbar} {Interviewing} {World} {Experts} on {Nuclear} {Energy}},
	url = {https://www.titansofnuclear.com/katyhuff},
	abstract = {?Show Titans Of Nuclear {\textbar} Interviewing World Experts on Nuclear Energy, Ep Ep. 145 - Katy Huff, University of Illinois - Apr 10, 2019},
	language = {en-us},
	urldate = {2019-04-12},
	journal = {Titans Of Nuclear {\textbar} Interviewing World Experts on Nuclear Energy},
	publisher = {Apple Podcasts},
	author = {Kugelmass, Bret},
	collaborator = {Huff, Kathryn D.},
	month = apr,
	year = {2019},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/D2I87WZJ/id1331598443.html:text/html},
}

@article{hu_someday_2019,
	title = {Someday the {U}.{S}. {Will} {Have} to {Actually} {Deal} {With} {Its} {Nuclear} {Waste} {Problem}},
	volume = {Technology},
	shorttitle = {Someday the {U}.{S}. {Will} {Have} to {Actually} {Deal} {With} {Its} {Nuclear} {Waste} {Problem}. {The} {Department} of {Energy} has made a move in that direction.},
	url = {https://slate.com/technology/2019/06/department-of-energy-nuclear-waste-reclassification-yucca.html},
	abstract = {The lack of solution is not from lack of discussion. There have been all sorts of wacky ideas floated about where to store nuclear waste.},
	language = {en},
	urldate = {2019-06-09},
	journal = {Slate Magazine},
	author = {Hu, Jane C.},
	month = jun,
	year = {2019},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/PD4VLBYM/department-of-energy-nuclear-waste-reclassification-yucca.html:text/html},
}

@techreport{heald_investigation_2018,
	address = {Urbana, IL},
	type = {{UIUC} {Technical} {Report}},
	title = {Investigation of {Agricultural} {Uses} of {Nuclear} {Waste} {Heat}. {UIUC} {Technical} {Report}. {October}, 2018.},
	abstract = {Nuclear power plants (NPPs) produce significant quantities of waste heat due to the low thermal efficiency of the Rankine cycle. This waste heat carries roughly two-thirds of the total power generated at a nuclear power plant. It is responsibly released to the environment as a warm water flow, carrying with it a massive amount of low-grade thermal energy. As of now, this energy is lost from all Exelon NPPs. This waste heat is essentially a free source of energy and utilization projects offer the potential to significantly increase the thermal efficiency and profitability of centralized power generating stations, in particular NPPs.
Agricultural projects, particularly climate-controlled greenhouses, may show the most dramatic benefit from waste-heat utilization. Due to the relatively low temperature requirements of greenhouses, heating costs may be eliminated or cut substantially by the implementation of waste heat. The technical readiness of coupling central power generation station{\textquoteright}s waste heat discharge to climate-controlled greenhouses is high and has been demonstrated. Implementing this combined heat and power approach to Exelon{\textquoteright}s fleet of NPPs could offer significant advantages over fossil fueled power plants due to their high capacity factor, and strictly controlled and monitored water discharge.   
Exelon NPPs at Braidwood, Byron, Dresden, and Calvert Cliffs hold potential to supply significant agricultural waste heat. Few regulations exist specific to the use of waste heat from NPPs, but the discharge of waste heat from NPPs is strictly regulated, mitigating potential for regulatory hurdles to its use in other industries. Waste heat from Exelon{\textquoteright}s NPPs is an untapped and potentially lucrative commodity. In the Midwest, the location of Exelon{\textquoteright}s NPPs offers interesting opportunities for waste heat use in agriculture. The cold Midwest climate is normally a limiting factor in crop diversity and heated greenhouses are an option for overcoming this issue, but the heating costs are a barrier themselves. With cooperation between growers and the Exelon Corporation, waste heat may be commoditized while also facilitating more efficient and diverse growing operations. Waste heat use is not limited to farming operations. There are a host of industries that can benefit from waste heat use that may be local to other power plants. The Calvert Cliffs Nuclear Power Plant is located ideally to facilitate the farming of oysters with waste heat or even provide heat for liquefied natural gas vaporization. 
This report details a preliminary analysis to evaluate the potential for utilizing waste heat from NPPs. From the exhaustive review of past waste heat efforts, agricultural options, and primary economic and radiological factors, the technical readiness is shown to be high and the concept is sound. It is recommended that a detailed analysis should follow that includes: coupling candidate NPPs to specific greenhouse architectures, exploration of high-value crop options in prototypic and bounding event environments, and a detailed economic assessment.},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Heald, Alexander L. and Miernicki, E.A. and Fairhurst, Roberto E. and Margenot, Andrew J. and Huff, Kathryn D. and Brooks, Caleb S.},
	month = oct,
	year = {2018},
	file = {Heald et al. - 2018 - Investigation of Agricultural Uses of Nuclear Wast.pdf:/Users/huff/Zotero/storage/8JH3NT4L/Heald et al. - 2018 - Investigation of Agricultural Uses of Nuclear Wast.pdf:application/pdf},
}

@techreport{sabharwall_micronuclear_2019,
	address = {Idaho Falls, ID},
	type = {{INL} {Limited} {Distribution}},
	title = {{MicroNuclear} {Battery} {Thermal} and {Fluid} {Analysis} and {Multiphysics} {Modeling} {Challenges}},
	shorttitle = {Contract {DE}-{AC07}-{05ID14517}},
	abstract = {Molten salt reactor technology has many distinct advantages. Although many challenges come wit ha molten salt system, the advantages of such a system outweigh the challenges. Many organizations worldwide have undertaken research and development of molten salt reactors, with the possibility of a commercially deployed reactor by 2030. However, there is still much to do for the development and deployment of molten salt reactor technology.},
	number = {INL/LTD-19-52963},
	institution = {Idaho National Laboratory},
	author = {Sabharwall, Piyush and Anderson, Nolan and Marotta, Paul and Christensen, Rich},
	collaborator = {Huff, Kathryn D. and Wendt, Daniel S. and Jesse, Casey J. and Roper, Robin},
	month = feb,
	year = {2019},
	file = {msr-multiphysics-gaps.pdf:/Users/huff/Zotero/storage/WVFDTSMR/msr-multiphysics-gaps.pdf:application/pdf;Sabharwall et al. - 2019 - MicroNuclear Battery Thermal and Fluid Analysis an.pdf:/Users/huff/Zotero/storage/CNMPL6GL/Sabharwall et al. - 2019 - MicroNuclear Battery Thermal and Fluid Analysis an.pdf:application/pdf},
}

@inproceedings{chaube_dynamic_2019,
	address = {Fukuoka, Japan},
	title = {Dynamic {Transition} {Analysis} with {TIMES}},
	booktitle = {{I2CNER} {Annual} {Symposium}},
	publisher = {Kyushu University},
	author = {Chaube, Anshuman and Stubbins, James and Huff, Kathryn D.},
	month = feb,
	year = {2019},
	note = {(Presentation)},
}

@misc{huff_open-source_2018,
	address = {Urbana, IL},
	type = {Poster},
	title = {Open-{Source} {Curriculum} {Development}},
	copyright = {CC-BY},
	shorttitle = {katyhuff/2018-04-20-siip},
	url = {https://zenodo.org/record/1245677},
	abstract = {This poster was presented on April 20, 2018 at the Academy for Excellence in Engineering Education (AE3) Celebration of Teaching at the University of Illinois. It describes the progress on the Open Source Curriculum Development SIIP. Kathryn Huff, Neal Davis, Paul Wilson, Robert Borrelli, Steven Skutnik, Jeremy Roberts, Anthony Scopatz. SIIP Liason: Jenny Amos.},
	language = {english},
	urldate = {2018-05-11},
	author = {Huff, Kathryn and Davis, Neal and Wilson, Paul P.H. and Borrelli, Robert and Skutnik, Steven and Roberts, Jeremy and Scopatz, Anthony and Amos, Jennifer},
	month = may,
	year = {2018},
	doi = {10.5281/zenodo.1245677},
	keywords = {open source, nuclear engineering, engineering education},
	file = {Kathryn Huff et al. - 2018 - katyhuff2018-04-20-siip Celebration of Teaching.pdf:/Users/huff/Zotero/storage/MZUCSGEY/Kathryn Huff et al. - 2018 - katyhuff2018-04-20-siip Celebration of Teaching.pdf:application/pdf;Zenodo Snapshot:/Users/huff/Zotero/storage/SJAJ8AWH/1245677.html:text/html},
}

@misc{huff_neutron_2019-1,
	address = {West Lafayette, IN, United States},
	type = {Seminar},
	title = {Neutron {Kinetics} and {Dynamics} in {Liquid}-{Fueled} {Nuclear} {Reactors}},
	abstract = {Modeling and simulation of neutron kinetics and dynamics in liquid-fueled, molten salt reactors incorporates three major challenging components. First, it is necessary to establish the dynamic  evolution of fuel composition via depletion and online reprocessing. Additionally, multiphysics analysis of the thermal hydraulics and neutronics in such a nuclear reactor must incorporate thermal feedbacks and material expansion feedbacks. Finally, drift of delayed neutron precursors must be incorporated into the kinetics analysis due to the mobility of the liquid fuel. This talk will discuss all three components. Toward the first component, a discussion of the SaltProc python package will establish the fuel composition dynamics capabilities necessary for fuel composition depletion in the context of online reprocessing. Toward the second component, a point kinetics model implementation in PyRK, and a more sophisticated advection model implementation in Moltres will be discussed, including neutron diffusion and precursor drift equations in Moltres as well as their implementation using the MOOSE action system. Finally, future directions for Moltres and SaltProc development will be noted.},
	author = {Huff, Kathryn D.},
	month = feb,
	year = {2019},
}

@misc{chaube_dynamic_2019-1,
	address = {I2CNER Annual Symposium, Fukuoka, Japan},
	title = {Dynamic {Transition} {Analysis} with {TIMES}},
	url = {http://arfc.github.io/pres/2019-02-01-chaube-i2cner.pdf},
	author = {Chaube, Anshuman},
	month = feb,
	year = {2019},
}

@inproceedings{bae_impact_2018-1,
	address = {Orlando, FL},
	title = {Impact of {Composition} {Approximation} on {Simulated} {Nuclear} {Fuel} {Cycle} {Metrics}},
	url = {http://arfc.npre.illinois.edu/pres/2018-11-13-bae-answinter2018.pdf},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} {Winter} {Meeting}},
	publisher = {American Nuclear Society},
	author = {Bae, Jin Whan and Peterson-Droogh, Joshua L. and Huff, Kathryn D.},
	month = nov,
	year = {2018},
}

@inproceedings{rykhlevskii_fuel_2019,
	address = {Portland, OR},
	title = {Fuel {Cycle} {Performance} of {Fast} {Spectrum} {Molten} {Salt} {Reactor} {Designs}},
	url = {http://epubs.ans.org/?a=46618},
	booktitle = {Proceedings of {Mathematics} and {Computation} 2019},
	publisher = {American Nuclear Society},
	author = {Rykhlevskii, Andrei and Betzler, Benjamin R. and Worrall, Andrew and Huff, Kathryn D.},
	month = aug,
	year = {2019},
	pages = {342--353},
	file = {Rykhlevskii et al. - 2019 - Fuel Cycle Performance of Fast Spectrum Molten Sal.pdf:/Users/huff/Zotero/storage/22VH9KTC/Rykhlevskii et al. - 2019 - Fuel Cycle Performance of Fast Spectrum Molten Sal.pdf:application/pdf},
}

@article{huff_fundamental_2016,
	title = {Fundamental concepts in the {Cyclus} nuclear fuel cycle simulation framework},
	volume = {94},
	issn = {0965-9978},
	url = {http://www.sciencedirect.com/science/article/pii/S0965997816300229},
	doi = {10.1016/j.advengsoft.2016.01.014},
	abstract = {As nuclear power expands, technical, economic, political, and environmental analyses of nuclear fuel cycles by simulators increase in importance. To date, however, current tools are often fleet-based rather than discrete and restrictively licensed rather than open source. Each of these choices presents a challenge to modeling fidelity, generality, efficiency, robustness, and scientific transparency. The Cyclus nuclear fuel cycle simulator framework and its modeling ecosystem incorporate modern insights from simulation science and software architecture to solve these problems so that challenges in nuclear fuel cycle analysis can be better addressed. A summary of the Cyclus fuel cycle simulator framework and its modeling ecosystem are presented. Additionally, the implementation of each is discussed in the context of motivating challenges in nuclear fuel cycle simulation. Finally, the current capabilities of Cyclus are demonstrated for both open and closed fuel cycles.},
	language = {en},
	urldate = {2016-02-12},
	journal = {Advances in Engineering Software},
	author = {Huff, Kathryn D. and Gidden, Matthew J. and Carlsen, Robert W. and Flanagan, Robert R. and McGarry, Meghan B. and Opotowsky, Arrielle C. and Schneider, Erich A. and Scopatz, Anthony M. and Wilson, Paul P. H.},
	month = apr,
	year = {2016},
	note = {arXiv: 1509.03604},
	keywords = {Simulation, Nuclear fuel cycle, Computer Science - Software Engineering, Computer Science - Mathematical Software, agent based modeling, Computer Science - Computational Engineering, Finance, and Science, Computer Science - Multiagent Systems, D.2.13, D.2.4, I.6.7, I.6.8, Object orientation, Systems analysis, nuclear engineering, simulation, Agent based modeling, Nuclear engineering, and Science, Computer Science - Computational Engineering, Finance},
	pages = {46--59},
	annote = {arXiv: 1509.03604},
	file = {arXiv\:1509.03604 PDF:/Users/huff/Zotero/storage/F9KVM9DZ/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv\:1509.03604 PDF:/Users/huff/Zotero/storage/4FI3T63Q/Huff et al. - 2015 - Fundamental Concepts in the Cyclus Fuel Cycle Simu.pdf:application/pdf;arXiv\:1509.03604 PDF:/Users/huff/Zotero/storage/GN7WIP38/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;arXiv.org Snapshot:/Users/huff/Zotero/storage/HXSDS7VW/1509.html:text/html;arXiv.org Snapshot:/Users/huff/Zotero/storage/WQVTXAN2/1509.html:text/html;arXiv.org Snapshot:/Users/huff/Zotero/storage/EVFA3LC6/1509.html:text/html;Fulltext:/Users/huff/Zotero/storage/3IMCACE5/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;fundamentals.pdf:/Users/huff/Zotero/storage/C6G4NQJH/fundamentals.pdf:application/pdf;fundamentals.pdf:/Users/huff/Zotero/storage/BRJECDWC/fundamentals.pdf:application/pdf;Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:/Users/huff/Zotero/storage/FAM6DNLV/Huff et al. - 2016 - Fundamental concepts in the Cyclus nuclear fuel cy.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/E7DK64AA/E7DK64AA.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/JCCZAZB3/S0965997816300229.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/EVBNKXMA/S0965997816300229.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/63CHUQ54/login.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/275X4LV5/S0965997816300229.html:text/html;Snapshot:/Users/huff/Zotero/storage/9DRDIPZV/S0965997816300229.html:text/html},
}

@inproceedings{huff_cyclus_2011,
	address = {Phoenix, AZ},
	title = {Cyclus: {An} {Open}, {Modular}, {Next} {Generation} {Fuel} {Cycle} {Simulator} {Platform} (poster)},
	abstract = {CYCLUS is a top-level, next generation, nuclear fuel cycle simulation framework designed with an open development process and modular platform. It employs lessons learned from previous efforts to pursue quantitative assessment of worldwide nuclear energy production, material flows, energy costs, environmental impact, proliferation resistance, and robustness against supply disruption.},
	booktitle = {Proceedings of the {Waste} {Management} {Symposium}},
	author = {Huff, Kathryn D.},
	month = mar,
	year = {2011},
	file = {WM2011.pdf:/Users/huff/Zotero/storage/ID9PP8PC/WM2011.pdf:application/pdf;WM2011.pdf:/Users/huff/Zotero/storage/ACQ4MUR5/WM2011.pdf:application/pdf},
}

@inproceedings{huff_genius_2009,
	address = {University of Wisconsin, Madison},
	title = {{GENIUS} {Version} 2: {Modeling} the {Worldwide} {Nuclear} {Fuel} {Cycle} (poster)},
	booktitle = {Proceedings of the {eHub} {Conference}},
	author = {Huff, Kathryn D. and Wilson, Paul P.H. and Oliver, Kyle M.},
	month = nov,
	year = {2009},
}

@inproceedings{huff_cyclus_2013,
	address = {Salt Lake City, UT, United States},
	series = {Nuclear {Fuel} {Cycle} and {Fuel} {Materials}},
	title = {Cyclus {Fuel} {Cycle} {Simulation} {Capabilities} with the {Cyder} {Disposal} {System} {Model}},
	volume = {45},
	url = {https://inis.iaea.org/search/search.aspx?orig_q=RN:45085412},
	booktitle = {Proceedings of {GLOBAL} 2013: {International} {Nuclear} {Fuel} {Cycle} {Conference}-{Nuclear} {Energy} at a {Crossroads}},
	author = {Huff, Kathryn D.},
	month = oct,
	year = {2013},
	file = {cyder.pdf:/Users/huff/Zotero/storage/BRUIU96K/cyder.pdf:application/pdf;huff_global_2013.pdf:/Users/huff/Zotero/storage/75K3EDPX/huff_global_2013.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/CTPH9CQQ/search.html:text/html},
}

@misc{hawksworth_nuclear_2018,
	address = {Chicago, IL, United States},
	title = {Nuclear {Engineering} {Programs} with {Dr}. {Kathryn} {Huff}},
	copyright = {YesCollege},
	shorttitle = {Ep 17},
	url = {https://yescollege.com/episode/kathryn-huff/},
	abstract = {On this week{\textquoteright}s show, we dive into the sciences and explore the exciting field of nuclear engineering! Scott was joined by Dr. Kathryn Huff, Assistant Professor in the Department of Nuclear, Plasma and Radiological Engineering and a Blue Waters Assistant Professor with the National Center for Supercomputing Applications at the University of Illinois at Urbana-Champaign. {\textellipsis}},
	language = {en-US},
	urldate = {2018-07-06},
	journal = {Yes College Podcast},
	publisher = {YesCollege.com},
	author = {Hawksworth, Scott},
	collaborator = {Huff, Kathryn D.},
	month = feb,
	year = {2018},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/ADXW3UJH/kathryn-huff.html:text/html},
}

@inproceedings{hague_comparison_2019,
	title = {A comparison of adaptive and template matching techniques for radio-isotope identification},
	volume = {10986},
	url = {https://www.spiedigitallibrary.org/conference-proceedings-of-spie/10986/1098608/A-comparison-of-adaptive-and-template-matching-techniques-for-radio/10.1117/12.2519062.short},
	doi = {10.1117/12.2519062},
	abstract = {We compare and contrast the effectiveness of a set of adaptive and non-adaptive algorithms for isotope identification based on gamma-ray spectra. One dimensional energy spectra are simulated for a variety of dwell-times and source to detector distances in order to reflect conditions typically encountered in radiological emergency response and environmental monitoring applications. We find that adaptive methods are more accurate and computationally efficient than non-adaptive in cases of operational interest.},
	urldate = {2019-10-30},
	booktitle = {Algorithms, {Technologies}, and {Applications} for {Multispectral} and {Hyperspectral} {Imagery} {XXV}},
	publisher = {International Society for Optics and Photonics},
	author = {Hague, Emma J. and Kamuda, Mark and Ford, William P. and Moore, Eric T. and Turk, Johanna},
	month = may,
	year = {2019},
	pages = {1098608},
	file = {Full Text PDF:/Users/huff/Zotero/storage/5ZBQBNJH/Hague et al. - 2019 - A comparison of adaptive and template matching tec.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/B5NG8X8D/12.2519062.html:text/html},
}

@article{anghel_krannert_2019,
	address = {Urbana, IL},
	chapter = {Around Campus},
	title = {Krannert exhibit raises awareness of nuclear industry},
	url = {https://dailyillini.com/news/2019/10/24/krannert-nuclear-industry/},
	abstract = {The Krannert Art Museum opened the {\textquotedblleft}Hot Spots: Radioactivity and the Landscape{\textquotedblright} exhibit on Thursday, taking on the role of bringing attention to the damage done by the nuclear industry on indigenous lands and posing questions of long-term plans for the future. First seen at the University at Buffalo, the exhibit was created for the...},
	language = {en, sv},
	urldate = {2019-10-25},
	journal = {The Daily Illini - The Independent Student Newspaper at the University of Illinois},
	author = {Anghel, Diana},
	collaborator = {Huff, Kathryn},
	month = oct,
	year = {2019},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/V3ZLJIZL/krannert-nuclear-industry.html:text/html;Snapshot:/Users/huff/Zotero/storage/L3DW7LPI/krannert-nuclear-industry.html:text/html},
}

@inproceedings{chee_simulation_2019,
	address = {Phoenix, AZ},
	title = {Simulation of {Spent} {Nuclear} {Fuel} loading into a {Final} {Waste} {Repository}},
	booktitle = {{WM} {Symposia} 2019 {Proceedings}},
	publisher = {Roy G. Post Foundation},
	author = {Chee, Gwendolyn J. and Huff, Kathryn D.},
	month = apr,
	year = {2019},
	file = {Gwendolyn J. Chee and Kathryn D. Huff - 2019 - Simulation of Spent Nuclear Fuel loading into a Fi.pdf:/Users/huff/Zotero/storage/8BZG9D2S/Gwendolyn J. Chee and Kathryn D. Huff - 2019 - Simulation of Spent Nuclear Fuel loading into a Fi.pdf:application/pdf},
}

@inproceedings{bae_synergistic_2017,
	address = {Washington, D.C.},
	series = {Fuel {Cycle} and {Waste} {Management}},
	title = {Synergistic {Spent} {Nuclear} {Fuel} {Dynamics} {Within} the {European} {Union}},
	volume = {117},
	url = {http://epubs.ans.org/?a=41265},
	abstract = {The French strategy recommended by 2012-2015 Commission
Nationale d{\textquoteright}Evaluation reports [1] emphasizes preparation
for a transition from Light Water Reactors (LWRs) to
Sodium-Cooled Fast Reactors (SFRs). This paper uses Cyclus
to explore the feasibility of using Used Nuclear Fuel (UNF)
from other EU nations for French transition into a SFR fleet
without additional construction of LWRs. A Cyclus simulation
is run from 1950 to 2160 for EU to track the UNF mass
and to determine the necessary reprocessing and mixed oxide
(MOX) fabrication capacity to support the transition into
SFRs. The study concludes that France can avoid deployment
of additional LWRs by accepting UNF from other EU nations.},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Winter} {Conference}},
	publisher = {American Nuclear Society},
	author = {Bae, Jin Whan and Huff, Kathryn and Singer, Clifford},
	month = oct,
	year = {2017},
	pages = {261--265},
	file = {europe_nuclear_paper.pdf:/Users/huff/Zotero/storage/KEJMSZTE/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/huff/Zotero/storage/LGFAP2BG/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/huff/Zotero/storage/MKKTZAGM/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/huff/Zotero/storage/NLNAKMUG/europe_nuclear_paper.pdf:application/pdf;europe_nuclear_paper.pdf:/Users/huff/Zotero/storage/ZP787VN4/europe_nuclear_paper.pdf:application/pdf},
}

@inproceedings{chee_numerical_2018,
	address = {Gainesville, FL, United States},
	title = {Numerical {Experiments} for testing {Demand}-{Driven} {Deployment} {Algorithms}},
	abstract = {For many fuel cycle simulators, it is currently up to the user to define a deployment scheme for each component of the fuel cycle to avoid gaps in the supply chain. This same goal could also be achieved by setting all the facility{\textquoteright}s ca- pacities to infinity. However, this does not reflect real-world conditions [1]. To address this gap in capability of fuel cycle simulators, the Demand-Driven Cycamore Archetype project (NEUP-FY16-10512) is developing prediction algorithms to give Cyclus demand-driven deployment capabilities. This means that Cyclus will have the capability to deploy sup- porting fuel cycle facilities to meet front-end and back-end demands of the fuel cycle. The project is a collaboration between the University of Illinois Urbana-Champaign and the University of South Carolina. This paper will discuss the numerical experiments required to test the various prediction algorithms designed for the project. In particular, this work describes tests for the non-optimizing algorithm.},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} 2018 {National} {Student} {Conference},},
	publisher = {American Nuclear Society},
	author = {Chee, Gwendolyn and Bae, Jin Whan and Huff, Kathryn D.},
	month = apr,
	year = {2018},
	file = {Chee et al. - 2018 - Numerical Experiments for testing Demand-Driven De.pdf:/Users/huff/Zotero/storage/ZWG7WHKJ/Chee et al. - 2018 - Numerical Experiments for testing Demand-Driven De.pdf:application/pdf;Fulltext:/Users/huff/Zotero/storage/8729QICM/Chee et al. - 2018 - Numerical Experiments for Testing Demand-Driven De.pdf:application/pdf;GwendolynChee-ansstuconf2018.pdf:/Users/huff/Zotero/storage/Z6KJXWVH/GwendolynChee-ansstuconf2018.pdf:application/pdf;GwendolynChee-ansstuconf2018.pptx:/Users/huff/Zotero/storage/3AMPECLL/GwendolynChee-ansstuconf2018.pptx:application/vnd.openxmlformats-officedocument.presentationml.presentation;Snapshot:/Users/huff/Zotero/storage/7I6MM7HM/Chee et al. - 2018 - Numerical Experiments for Testing Demand-Driven De.pdf:application/pdf},
}

@mastersthesis{rykhlevskii_advanced_2018,
	address = {Urbana, IL},
	title = {Advanced  online fuel reprocessing simulation for {Thorium}-fueled {Molten} {Salt} {Breeder} {Reactor}},
	copyright = {Copyright 2018 Andrei Rykhlevskii},
	shorttitle = {Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor},
	url = {https://www.ideals.illinois.edu/handle/2142/101052},
	abstract = {Current interest in advanced nuclear energy and MSR concepts has enhanced demand in building the tools to analyze these systems. This thesis introduces a Python script, SaltProc, which simulates MSR online reprocessing by modeling the changing isotopic composition of an irradiated fuel salt. SaltProc couples with the Monte Carlo code, SERPENT 2, for neutron transport and depletion calculations. SaltProc capabilities include a generic geometry capable of modeling multi-region and multi-flow systems, time-dependent feeds and removals, and specific separation efficiency for each element or isotope removal flow. Generally applicable capabilities are illuminated in this thesis in three applied problems: (1) simulating the startup of a thorium-fueled MSBR fuel cycle to find equilibrium fuel composition (when multiplication factor of the full-core model and the U-233 concentration in the fuel salt are invariant in time); (2) determining the effect of the fuel salt irradiation with online reprocessing on MSBR operations; and (3) estimating MSBR fuel cycle performance by computing the Th-232 feed rate over 20 years of operation and comparing with available data. In the first application, full-core depletion in the MSBR demonstrated that (1) equilibrium fuel composition could be achieved after 16 years and (2) the multiplication factor stabilizes after 6 years of operation. In the second application, fuel salt irradiation with simulated fission product removal and fissile/fertile feed causes considerable neutron energy spectrum hardening; this spectral shift has a problematic impact on safety parameters (e.g., temperature reactivity feedback, reactivity control system worth). In the third application, the average Th-232 feed rate throughout 20 years of operation is 2.39 kg/day or 100 g/GWh(e) which is a good agreement with other recent research. Problematic effects of neutron energy spectrum hardening during MSBR operation should be taken into account for neutronics, multi-physics, and fuel cycle performance analysis.},
	language = {English},
	urldate = {2018-09-27},
	school = {University of Illinois at Urbana-Champaign},
	author = {Rykhlevskii, Andrei},
	collaborator = {Kozlowski, Tomas and Huff, Kathryn},
	month = apr,
	year = {2018},
	file = {Fulltext:/Users/huff/Zotero/storage/SBUDQM3I/Rykhlevskii - 2018 - Advanced online fuel reprocessing simulation for t.pdf:application/pdf;ms_rykhlevskii_msbr_reproc.pdf:/Users/huff/Zotero/storage/EI334QNX/ms_rykhlevskii_msbr_reproc.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/LWTBSFX7/101052.html:text/html},
}

@mastersthesis{bae_fuel_2018,
	address = {Urbana, IL},
	title = {Fuel cycle transition simulation capabilities in {CYCLUS}},
	copyright = {Copyright 2018 Jin Whan Bae},
	url = {https://www.ideals.illinois.edu/handle/2142/102517},
	abstract = {Recent interest in advanced reactors and the following need for techno-economic transitions has increased the demand for tools necessary to model complex nuclear fuel cycles (NFCs) and advanced reactor technologies. This thesis demonstrates the capability of CYCLUS , the agent-based fuel cycle simulator, to model, simulate, and analyze real-life fuel cycle transition scenarios. I introduce new methods and tools that use various databases to model and simulate real-world nuclear fuel cycle transition scenarios involving advanced reactor technologies.

The work in this thesis contains: (1) benchmarking Cyclus to other nuclear fuel cycle simulators (NFC simulators); (2) developing new methods and tools necessary for modeling and simulating real-world fuel cycle transition scenarios; (3) simulation of both domestic and international nuclear technology transitions.

The methods and tools developed for such capabilities include: (1) modeling and simulating past and current nuclear fleets using historic nuclear reactor operations database; (2) modeling individual reactors and their operating history to calculate nuclear material inventory; (3) modeling Molten Salt Reactor (MSR) behavior in a large-scale fuel cycle simulation.

Benchmark work shows that CYCLUS results coincide with results from other NFC simulators with minor differences due to modeling choices. Additionally, this thesis demonstrates the CYCLUS capability to effectively model and simulate real-life NFC transition scenarios that involve advanced reactor technologies such as MSRs.},
	language = {en},
	urldate = {2019-06-13},
	school = {University of Illinois at Urbana-Champaign},
	author = {Bae, Jin Whan},
	month = dec,
	year = {2018},
	file = {Full Text PDF:/Users/huff/Zotero/storage/NAP77Q4U/Bae - 2018 - Fuel cycle transition simulation capabilities in C.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/RMWZTFLG/102517.html:text/html},
}

@misc{rykhlevskii_fuel_2019-1,
	address = {Portland, OR, United States},
	type = {Conference},
	title = {Fuel {Cycle} {Performance} of {Fast} {Spectrum} {Molten} {Salt} {Reactor} {Designs}},
	abstract = {This presentation shows progress in fuel cycle performance evaluation for 4 different fast molten salt reactors.},
	language = {English},
	author = {Rykhlevskii, Andrei},
	collaborator = {Betzler, Benjamin and Bae, Jin Whan and Huff, Kathryn},
	month = aug,
	year = {2019},
	file = {Rykhlevskii - 2019 - Fuel Cycle Performance of Fast Spectrum Molten Sal.pdf:/Users/huff/Zotero/storage/3SIXCH7U/Rykhlevskii - 2019 - Fuel Cycle Performance of Fast Spectrum Molten Sal.pdf:application/pdf},
}

@article{chaube_tap_2019,
	title = {{TAP} {MSR} model for {Serpent} 2},
	doi = {10.5281/zenodo.1450733},
	urldate = {2018-10-08},
	journal = {Zenodo},
	author = {Chaube, Anshuman and O'Grady, Daniel and Rykhlevskii, Andrei and Huff, Kathryn D.},
	year = {2019},
	file = {Zenodo Snapshot:/Users/huff/Zotero/storage/T78KIUBM/1450733.html:text/html},
}

@techreport{rykhleskii_removal_2018,
	address = {Urbana, IL},
	type = {Technical {Report}},
	title = {Removal of {Rare} earths from {FLiBe} in a single-fluid {Molten} {Salt} {Reactor}},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Rykhleskii, Andrei},
	month = dec,
	year = {2018},
	keywords = {arfc, report},
	pages = {0--9},
	file = {Rykhleskii - 2018 - Removal of Rare earths from FLiBe in a single-flui.pdf:/Users/huff/Zotero/storage/9AB8J2K8/Rykhleskii - 2018 - Removal of Rare earths from FLiBe in a single-flui.pdf:application/pdf},
}

@techreport{chaube_dynamic_2019-2,
	address = {Urbana, IL},
	type = {Technical {Report}},
	title = {Dynamic {Transition} {Analysis} {With} {The} {Integrated} {Markal}-{EFOM} {System} ({TIMES}): {International} {Institute} for {Carbon}-{Neutral} {Energy} {Research} ({I2CNER}) {Project} {Report}},
	url = {https://zenodo.org/record/3354538#.XT9WlpNKirw},
	abstract = {We initiated a project in January 2018 to simulate dynamic transition scenarios for the energy industry in Japan to suggest pathways for minimizing carbon emissions. This report is a summary of the progress we have made so far, the challenges we currently face, and the future direction of this research.},
	language = {eng},
	number = {UIUC-ARFC-2019-02},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Chaube, Anshuman and Huff, Kathryn D. and Stubbins, James},
	collaborator = {Itaoka, Kenshi and Chapman, Andrew and Faradi, Hadi},
	month = may,
	year = {2019},
	doi = {10.5281/zenodo.3354538},
	keywords = {arfc, report, i2cner, energy analysis, japan},
	pages = {0--17},
	annote = {The authors gratefully acknowledge the support of the International Institute for Carbon Neutral Energy Research (WPI-I2CNER), sponsored by the Japanese Ministry of Education, Culture, Sports, Science and Technology.},
	file = {Zenodo Full Text PDF:/Users/huff/Zotero/storage/TGLY26H3/Anshuman Chaube and Kathryn Huff - 2019 - Dynamic Transition Analysis With The Integrated Ma.pdf:application/pdf},
}

@techreport{huff_identifying_2019,
	address = {Urbana, IL},
	type = {Technical {Report}},
	title = {Identifying {MSR} {Multiphysics} {Modeling} {Challenges}},
	shorttitle = {Contract {DE}-{AC07}-{05ID14517}},
	url = {https://zenodo.org/record/335456},
	abstract = {Solid fueled nuclear reactors differ from liquid fueled reactors with re- spect to many physical domains including neutronics, thermal hydraulics, and materials performance. Accordingly, liquid fueled reactors challenge the capabilities of conventional computational tools designed for modeling and simulating the physics of solid fueled reactors.},
	language = {english},
	number = {UIUC-ARFC-2019-01},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Huff, Kathryn D.},
	collaborator = {Sabharwall, Piyush},
	month = feb,
	year = {2019},
	doi = {10.5281/zenodo.3354563},
	keywords = {nuclear, molten salt reactor, multiphysics},
	pages = {1--12},
	annote = {This research was performed using funding received from Battelle Energy Alliance LLC, Idaho National Laboratory Standard Research Contract 214196.},
	file = {uiuc-arfc-2019-01.pdf:/Users/huff/Zotero/storage/CSVHID3A/uiuc-arfc-2019-01.pdf:application/pdf;Zenodo Full Text PDF:/Users/huff/Zotero/storage/RI2BAY9M/Kathryn Huff - 2019 - Identifying MSR Multiphysics Modeling Challenges.pdf:application/pdf},
}

@article{bae_arfc/transition-scenarios:_2018-1,
	title = {arfc/transition-scenarios: {Standardized} {Verification} of the {Cyclus} {Fuel} {Cycle} {Simulator}},
	volume = {GitHub},
	shorttitle = {arfc/transition-scenarios},
	doi = {10.5281/zenodo.1419110},
	abstract = {This release contains code and Cyclus input files to reproduce the plots used in the paper Standardized Verification of the Cyclus Fuel Cycle Simulator by Jin Whan Bae, Joshua L. Peterson-Droogh, and Kathryn D. Huff.},
	journal = {Zenodo},
	author = {Bae, Jin Whan and Park, Gyutae and Chee, Gwendolyn and Huff, Kathryn and Kennelly, Tyler and Speaks, PEP8 and Wilson, Paul and Scopatz, Anthony},
	month = sep,
	year = {2018},
	file = {Zenodo Snapshot:/Users/huff/Zotero/storage/ULXYFYNJ/1419110.html:text/html;Zenodo Snapshot:/Users/huff/Zotero/storage/WCNZYD46/1419110.html:text/html},
}

@techreport{chee_transition_2019,
	address = {Urbana, IL},
	type = {Technical {Report}},
	title = {Transition {Scenario} {Demonstrations} of {CYCAMORE} {Demand} {Driven} {Deployment} {Capabilities}},
	shorttitle = {Contract {DE}-{NE0008567}},
	url = {https://zenodo.org/record/3354507},
	abstract = {In many fuel cycle simulators, the user must define a deployment scheme for all supporting facilities to avoid supply chain gaps. To ease setting up nuclear fuel cycle simulations, Nuclear Fuel Cycle (NFC) simulators should bring demand-responsive deployment decisions into the dynamics of the simulation logic. Thus, a next-generation NFC simulator should predictively and automatically deploy fuel cycle facilities to meet a user-defined power demand. CYCLUS is an agent-based nuclear fuel cycle simulation framework [4]. In CYCLUS, each entity (i.e. Region, Institution, or Facility) in the fuel cycle is an agent. Region agents represent geographical or political areas that institution and facility agents can be grouped into. Institution agents control the deployment and decommission of facility agents and represents legal operating organizations such as a utility, government, etc. Facility agents represent nuclear fuel cycle facilities. CYCAMORE provides agents to represent process physics of various components in the nuclear fuel cycle (e.g. mine, fuel enrichment facility, reactor). The Demand-Driven CYCAMORE Archetypes project (NEUP-FY16-10512) aims to develop CYCLUS{\textquoteright} demand-driven deployment capabilities. This capability is added as a CYCLUS Institution agent that deploys facilities to meet the front-end and back-end fuel cycle demands based on a user-defined commodity demand. This demand-driven deployment capability is called d3ploy. In this paper, we explain the capabilities of d3ploy and demonstrate how d3ploy minimizes undersupply of all commodities in a few simulations while meeting key simulation constraints. Constant, linearly increasing, and sinusoidal power demand transition scenarios are demonstrated. Insights are discussed to inform parameter input decisions for future work in setting up larger transition scenarios that include many facilities. And finally, the more complex transition scenarios are demonstrated.},
	language = {english},
	number = {UIUC-ARFC-2019-03},
	urldate = {2019-07-29},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Chee, Gwendolyn and Fairhurst, Roberto and Huff, Kathryn},
	month = jun,
	year = {2019},
	note = {https://zenodo.org/record/3354507},
	keywords = {cyclus, arfc, report, nuclear fuel cycle},
	pages = {1--23},
	annote = {This research is being performed using funding received from the Department of Energy (DOE) Office of Nuclear Energy's Nuclear Energy University Program (Project 16-10512, DE-NE0008567) 'Demand-Driven Cycamore Archetypes'.},
	file = {Chee - 2019 - Transition Scenario Demonstrations of ARFC CYCAMOR.pdf:/Users/huff/Zotero/storage/RV5PZF3E/Chee - 2019 - Transition Scenario Demonstrations of ARFC CYCAMOR.pdf:application/pdf;Zenodo Full Text PDF:/Users/huff/Zotero/storage/FZWMCLYT/Gwendolyn Chee et al. - 2019 - Transition Scenario Demonstrations of CYCAMORE Dem.pdf:application/pdf},
}

@mastersthesis{chee_sensitivity_2019,
	address = {Urbana, IL},
	title = {Sensitivity {Analysis} of {Nuclear} {Fuel} {Cycle} {Transitions}},
	copyright = {Copyright 2019 Gwendolyn Jin Yi Chee},
	url = {https://www.ideals.illinois.edu/handle/2142/106272},
	abstract = {The present United States nuclear fuel cycle faces challenges that hinder the expansion of nuclear energy technology. The U.S. Department of Energy identi ed four classes of nuclear fuel cycle options the U.S could transition to, which would overcome these challenges and make nuclear energy technology more desirable. The transitions have been modeled by various nuclear fuel cycle simulators. However, most fuel cycle simulators require the user to define a deployment
scheme for all supporting facilities to avoid any supply chain gaps, which becomes tedious for complex transition scenarios. This thesis developed a capability in Cyclus, a nuclear fuel cycle
simulator, to automatically deploy fuel cycle facilities to meet user-defined power demand. This new capability successfully deployed fuel cycle facilities in a transition scenario from the current light water reactor fleet to a closed fuel cycle with continuous recycling of transuranics in fast and thermal reactors. In reality, these transition scenarios inevitably diverge from the modeled scenario. This work coupled the nuclear fuel cycle simulator tools, Cyclus and DYMOND, with Dakota, a
sensitivity analysis toolkit. This work conducted one-at-a-time, synergistic, and global sensitivity analysis with Cyclus-Dakota and DYMOND-Dakota, to understand the interdependence of input
parameters on the transition performance from the current light water reactor 
eet to a closed fuel cycle in which transuranics are recycled to fuel mixed oxide fuel thermal reactors and sodium fast-cooled reactors. The global sensitivity analysis concluded that the transition year input parameter was the most influential to the final depleted uranium and total idle reactor capacity performance
metrics, and the fleet share ratio and cooling time input parameters were the most influential to the final high level waste amount in the simulation. The one-at-a-time sensitivity analysis showed
that varying transition year from 80 to 84 years increased the final depleted uranium amount by 1.13\% and reduced the total idle reactor capacity by 10.36\%. The one-at-a-time sensitivity analysis also showed that varying fleet share ratio (mixed oxide fuel light water reactor: sodium fast-cooled reactor) from 0:100 to 20:80 reduced the final high level waste amount by 2\%, and varying the used fuel cooling time from 0 to 8 years reduced the final high level waste amount by 4\%. Therefore, an optimized transition scenario that minimizes final high level waste amount, final depleted uranium amount, and total idle capacity must have a fleet share ratio of 20:80, used fuel cooling time of 8
years, and a transition year at 83 years. This work compared Cyclus-Dakota's and DYMOND-Dakota's sensitivity analysis capabilities and concluded that automated deployment of supporting fuel cycle facilities is crucial for conducting sensitivity analyses with nuclear fuel cycle simulators, to ensure that the simulation adapts to the new parameters by minimizing idle reactor capacity.
The results demonstrated that time is saved if a comprehensive sensitivity analysis of a nuclear fuel cycle transition scenario begins with a global sensitivity analysis study to gain a general overview of the influential input variables for the performance metrics. Then, based on the global sensitivity analysis results, a reduced number of one-at-a-time and synergistic sensitivity analyses are conducted to determine quantitative trends and impacts of influential input variables on the performance metrics.},
	language = {English},
	school = {University of Illinois at Urbana-Champaign},
	author = {Chee, Gwendolyn J.},
	collaborator = {Huff, Kathryn D. and Stubbins, James},
	year = {2019},
	file = {gwen-ms-thesis-12-10.pdf:/Users/huff/Zotero/storage/DHGLM59Y/gwen-ms-thesis-12-10.pdf:application/pdf},
}

@mastersthesis{westphal_modeling_2019,
	address = {Urbana, IL},
	title = {Modeling {Special} {Nuclear} {Material} {Diversion} from a {Pyroprocessing} {Facility}},
	copyright = {Copyright 2019 Greg Westphal},
	abstract = {As a result of the once-through fuel cycle implemented in the US, used nuclear fuel (UNF)
steadily increases. One proposed solution is the transition to a closed nuclear fuel cycle, in
which reprocessing reduces build up of UNF. Pyroprocessing is an attractive method for this
transition for its capabilities separating both light water reactor (LWR) and metallic fuels,
and inherent proliferation resistance. However, unlike aqueous reprocessing plants, industrial pyroprocessing plants do not yet exist. Similar to safety-by-design in next-generation
reactors, reprocessing facilities could be designed with safeguards in mind via safeguardsby-design. Without operational experience, these safeguards-by-design need to be derived
through modeling and simulation.
This thesis develops a medium fidelity generic model, Pyre, capable of simulating a variety
of pyroprocessing facility configurations. Pyre also simulates diversion via a diverter class
capable of tracking signatures and observables. Rather than only tracking exact material
production, we use signatures and observables such as operating temperature, pressure, and
current to mimic the capabilities of International Atomic Energy Agency (IAEA) inspections
and aid identification of nefarious fuel cycles, or shadow fuel cycles.
These capabilities are verified in a transition scenario of the current US fuel cycle to a
sodium fast reactor (SFR) based closed fuel cycle. Key operating parameters are determined
through sensitivity analysis of this scenario, monitoring isotopic changes in material unaccounted for. This work concludes that facility parameters which increase interaction between
the salt and waste have more impact on material unaccounted for (MUF). This work also
expands the state of the art by exploring the use of sub-facility modeling to increase fuel
cycle fidelity.},
	language = {English},
	school = {University of Illinois at Urbana-Champaign},
	author = {Westphal, Greg},
	month = dec,
	year = {2019},
	file = {Westphal_2019_Modeling Special Nuclear Material Diversion from a Pyroprocessing Facility.pdf:/Users/huff/Zotero/storage/MY6TQ3RP/Westphal_2019_Modeling Special Nuclear Material Diversion from a Pyroprocessing Facility.pdf:application/pdf},
}

@inproceedings{betzler_impacts_2019,
	address = {Seattle, WA, United States},
	title = {Impacts of {Fast}-{Spectrum} {Molten} {Salt} {Reactor} {Characteristics} on {Fuel} {Cycle} {Performance}},
	url = {http://epubs.ans.org/?a=46968},
	booktitle = {Proceedings of {GLOBAL} {International} {Fuel} {Cycle} {Conference}},
	publisher = {American Nuclear Society},
	author = {Betzler, Benjamin R. and Rykhlevskii, Andrei and Worrall, Andrew and Huff, Kathryn D.},
	month = sep,
	year = {2019},
	file = {Full Text:/Users/huff/Zotero/storage/NAL94YJC/Betzler et al. - 2019 - Impacts of Fast-Spectrum Molten Salt Reactor Chara.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/SNHMA7NT/1566987.html:text/html},
}

@inproceedings{park_safety_2019,
	address = {Seattle, WA, United States},
	title = {Safety {Analysis} of the {Molten} {Salt} {Fast} {Reactor} {Fuel} {Composition} using {Moltres}},
	url = {http://epubs.ans.org/?a=47030},
	doi = {10.31224/osf.io/7ce89},
	abstract = {The Molten Salt Fast Reactor (MSFR) has garnered much interest for its inherent safety and sustainbility features. The MSFR can adopt a closed thorium fuel cycle for sustainable operation through the breeding of 233 U from 232 Th. The fuel composition changes significantly over the course of its lifespan. In this study, we investigated the steady state and transient behavior of the MSFR using Moltres, a coupled neutronics/thermal-hydraulics code developed within the Multiphysics Object Oriented Simulation Environment (MOOSE) framework. Three different fuel compositions, start-up, early-life, and equilibrium, were examined for potentially dangerous core temperature excursions during a unprotected loss of heat sink (ULOHS) accident. The six-group and total neutron flux distributions showed good agreement with SERPENT and published MSFR results, while the temperature distribution and total power showed discrepancies which can be attributed toknown sources of error. For the transient behavior under the ULOHS scenario, while the transition time towards the new steady state core temperature is also in good agreement with existing MSFR simulations by Fiorina et al., Moltres under-estimated the temperature rise by a factor of ten, due to the same sources of error affecting the steady state results. While an MSFR loaded with start-up fuel composition operates at a higher temperature than with the other two fuel compositions, all three cases were shown to be inherently safe due to thestrong negative temperature feedback.},
	urldate = {2019-11-05},
	booktitle = {Proceedings of {GLOBAL} {International} {Fuel} {Cycle} {Conference}},
	publisher = {American Nuclear Society},
	author = {Park, Sun Myung and Rykhlevskii, Andrei and Huff, Kathryn},
	month = sep,
	year = {2019},
	file = {Park et al. - 2019 - Safety Analysis of Molten Salt Fast Reactor Fuel C.pdf:/Users/huff/Zotero/storage/EXYUTUGW/Park et al. - 2019 - Safety Analysis of Molten Salt Fast Reactor Fuel C.pdf:application/pdf},
}

@misc{chee_arfc/dcwrapper_2019,
	title = {arfc/dcwrapper : {Gwen}'s {MS} {Thesis} {Release}},
	shorttitle = {arfc/dcwrapper},
	url = {https://doi.org/10.5281/zenodo.3530964},
	abstract = {This version of dcwrapper was used to create the results in @gwenchee's MS Thesis. This release creates a doi for this version of the project.},
	urldate = {2017-08-31},
	publisher = {Advanced Reactors and Fuel Cycles Research Group},
	author = {Chee, Gwendolyn and Westphal, Gregory and Huff, Kathryn},
	year = {2019},
	doi = {10.5281/zenodo.3530964},
	file = {arfc/dcwrapper\: dcwrapper v1.0 | Zenodo:/Users/huff/Zotero/storage/6ELE4QQB/3530964.html:text/html},
}

@inproceedings{rykhlevskii_impact_2019,
	address = {Washington, DC, United States},
	title = {The {Impact} of {Xenon}-135 on {Load} {Following} {Transatomic} {Power} {Molten} {Salt} {Reactor}},
	volume = {121},
	url = {http://epubs.ans.org/?a=47853},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Rykhlevskii, Andrei and O'Grady, Daniel and Kozlowski, Tomasz and Huff, Kathryn D.},
	month = nov,
	year = {2019},
	pages = {1441--1444},
	file = {Rykhlevskii et al. - 2019 - The Impact of Xenon-135 on Load Following Transato.pdf:/Users/huff/Zotero/storage/FS387NEW/Rykhlevskii et al. - 2019 - The Impact of Xenon-135 on Load Following Transato.pdf:application/pdf},
}

@inproceedings{dotson_optimal_2020,
	address = {Raleigh, N.C.},
	title = {Optimal {Sizing} of a {Micro}-{Reactor} for {Embedded} {Grid} {Systems}},
	abstract = {There has been significant work recently to develop en- ergy system concepts that incorporate a mixture of nuclear energy, variable renewable energy (VRE) and energy storage techniques. These systems are often referred to as nuclear hy- brid energy systems (NHES) and are generally robust, reliable, economically appealing, and have low to zero greenhouse gas (GHG) emissions [1, 2, 3, 4]. In 2015, the University of Illi- nois at Urbana-Champaign (UIUC) made a commitment to reach carbon neutrality by 2050 in the Illinois Climate Ac- tion Plan (iCAP) [5]. This plan identified nuclear energy as a potential contributor to this goal. In this work we use the RAVEN framework to find the optimal size for a micro-reactor that would minimize the levelized cost of electricity (LCOE) for the UIUC embedded grid. The greatest source economic variability is contained in the capital costs of a micro-reactor. Thus we examine both scenarios where the reactor is provided at no cost to the university and purchased at full price.},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Student} {Conference}},
	publisher = {American Nuclear Society},
	author = {Dotson, Samuel G. and Huff, Kathryn D.},
	month = mar,
	year = {2020},
	file = {Dotson and Huff - 2020 - Optimal Sizing of a Micro-Reactor for Embedded Gri.pdf:/Users/huff/Zotero/storage/XL93Z3I5/Dotson and Huff - 2020 - Optimal Sizing of a Micro-Reactor for Embedded Gri.pdf:application/pdf},
}

@article{rykhlevskii_arfc/saltproc:_2018,
	title = {arfc/saltproc: {Code} for online reprocessing simulation of molten salt reactor with external depletion solver {SERPENT}},
	doi = {10.5281/zenodo.1306628},
	abstract = {The script is re-run SERPENT 2 burnup simulation, and after each step removes target isotopes with specific efficiency, keep number density of target isotopes constant and keep track of Pa-233 --{\textgreater} U-233 decaying in the separate tank.},
	urldate = {2018-03-15},
	journal = {Zenodo},
	author = {Rykhlevskii, Andrei and Bae, Jin Whan and Huff, Kathryn},
	month = jul,
	year = {2018},
	keywords = {MSR, Fuel cycle, MSBR, online refueling, online reprocessing, salt separations, salt treatment, thorium cycle},
	file = {Zenodo Snapshot:/Users/huff/Zotero/storage/Z6YA3XBL/1196455.html:text/html;Zenodo Snapshot:/Users/huff/Zotero/storage/7YGYH6A6/1196455.html:text/html},
}

@incollection{huff_chapter_2019,
	address = {Cambridge, MA, United States},
	edition = {1},
	title = {Chapter {One} - {Economics} of {Advanced} {Reactors} and {Fuel} {Cycles}},
	volume = {1},
	isbn = {978-0-12-813975-2},
	url = {http://www.sciencedirect.com/science/article/pii/B9780128139752000016},
	abstract = {Many dynamic factors influence nuclear reactor and fuel cycle economics. Costs drive the equation, but policies affecting electricity pricing also influence nuclear power revenues at a fundamental level. In current reactors and their associated fuel cycles, capital, operation, and maintenance costs increasingly dominate the economics of nuclear power.
Advanced reactor designs and fuel cycle choices can impact these costs both positively
and negatively. While fuel cycle advancements also impact fuel costs, this component has a relatively small impact on the overall cost of nuclear electricity production, particularly in comparison to capital costs. If advanced reactors can offer very high-temperature heat appropriate for industrial processing, natively couple with storage technologies, or can otherwise acheive load following behavior, then they may become more financially feasible than the current fleet.},
	booktitle = {Storage and {Hybridization} of {Nuclear} {Energy}},
	publisher = {Science \& Technology Books Elsevier, Inc.},
	author = {Huff, Kathryn},
	editor = {Bindra, Hitesh},
	month = jan,
	year = {2019},
	doi = {10.1016/B978-0-12-813975-2.00001-6},
	keywords = {Economics, Levelized cost of electricity, Reprocessing, Enrichment, Advanced nuclear fuel cycles, Advanced nuclear reactors, Conversion, Fuel cycles, Fuel fabrication, Milling, Mining, Waste management},
	pages = {1--20},
	file = {Huff - 2018 - Economics of Advanced Reactors and Fuel Cycles (In.pdf:/Users/huff/Zotero/storage/A82V2LSU/Huff - 2018 - Economics of Advanced Reactors and Fuel Cycles (In.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/5KJ27BJ8/Huff - 2019 - Chapter One - Economics of Advanced Reactors and F.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/N84EB2DY/B9780128139752000016.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/N6A4JEIS/B9780128139752000016.html:text/html},
}

@misc{chee_arfc/d3ploy:_2019,
	title = {arfc/d3ploy: {A} collection of {Cyclus} manager archetypes for demand driven deployment},
	copyright = {BSD-3-Clause},
	shorttitle = {d3ploy},
	url = {https://github.com/arfc/d3ploy},
	abstract = {This release contains code to reproduce the results and plots in the NEUP final quarterly project, global 2019 presentations, and DDCA journal article.},
	urldate = {2018-08-06},
	publisher = {ARFC},
	author = {Chee, Gwendolyn J. and Bae, Jin Whan and Fairhurst, Roberto and Flanagan, Robert R. and Scopatz, Anthony M.},
	collaborator = {Huff, Kathryn D.},
	month = sep,
	year = {2019},
	note = {10.5281/zenodo.3464123},
	file = {arfc/d3ploy\: d3ploy v1.0.1-rc | Zenodo:/Users/huff/Zotero/storage/W4UWHPX5/3464123.html:text/html},
}

@article{ashraf_whole_2020,
	title = {Whole core analysis of the single-fluid double-zone thorium molten salt reactor ({SD}-{TMSR})},
	volume = {137},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454919306255},
	doi = {https://doi.org/10.1016/j.anucene.2019.107115},
	abstract = {The SD-TMSR (2,250 MWth) is a Single-fluid Double-zone Thorium-based Molten Salt Reactor. The active core of the SD-TMSR is divided into the inner zone (486 fuel tubes) and the outer zone (522 fuel tubes) to improve the Th-U3 breeding performance. This work adopted the SERPENT-2 Monte Carlo code to analyze the whole core model of the SD-TMSR. Built-in SERPENT-2 capabilities simulated online reprocessing and refueling and calculated the multiplication factor and Breeding Ratio (BR). We found that the molten salt Temperature Coefficient of Reactivity ($\alpha$T) was negative for initial and equilibrium states. This study investigated the variation of the multiplication factor, BR, and build-up of important nuclides in the core as a function of burnup. Under online reprocessing and refueling, we studied the variation of the reactivity during 60 years of reactor operation. Additionally, the neutron spectrum shift during the reactor operation was calculated. Finally, these simulations determined the appropriate 232Th and 233U feed rates for maintaining criticality and enabled analysis of the overall SD-TMSR fuel cycle performance.},
	language = {en},
	journal = {Annals of Nuclear Energy},
	author = {Ashraf, O. and Rykhlevskii, Andrei and Tikhomirov, G.V. and Huff, Kathryn D.},
	month = mar,
	year = {2020},
	keywords = {Burnup, Online reprocessing, MSR, Thorium fuel cycle, Breeding reactor, Monte carlo code},
	pages = {107--115},
	file = {ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/IUEQ9KGP/Ashraf et al. - 2019 - Whole core analysis of the single-fluid double-zon.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/X8N4UACM/S0306454919306255.html:text/html},
}

@article{kamuda_comparison_2020,
	series = {Symposium on {Radiation} {Measurements} and {Applications} {XVII}},
	title = {A comparison of machine learning methods for automated gamma-ray spectroscopy},
	volume = {954},
	issn = {0168-9002},
	url = {http://www.sciencedirect.com/science/article/pii/S0168900218313779},
	doi = {10.1016/j.nima.2018.10.063},
	abstract = {Pattern recognition algorithms such as artificial neural networks (NNs) and convolution neural networks (CNNs) are prime candidates to perform automated gamma-ray spectroscopy. The way these models train and operate mimic how trained spectroscopists identify spectra. These models have shown promise in identifying gamma-ray spectra with large calibration drift and unknown background radiation fields. In this work, two algorithms for mixtures of radioisotopes based on NN and CNN are presented and evaluated.},
	language = {en},
	urldate = {2020-01-28},
	journal = {Nuclear Instruments and Methods in Physics Research Section A: Accelerators, Spectrometers, Detectors and Associated Equipment},
	author = {Kamuda, Mark and Zhao, Jifu and Huff, Kathryn},
	month = feb,
	year = {2020},
	keywords = {Automated isotope identification, Gamma-ray spectroscopy, Neural networks},
	pages = {161385},
	file = {ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/F5ALG4UY/Kamuda et al. - 2018 - A comparison of machine learning methods for autom.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/RQ2N9TKJ/Kamuda et al. - 2020 - A comparison of machine learning methods for autom.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/NJB6SVXR/Kamuda et al. - 2020 - A comparison of machine learning methods for autom.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/PG4A68CJ/S0168900218313779.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/BD2NFXV9/S0168900218313779.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/MZ2HLMXB/S0168900218313779.html:text/html},
}

@inproceedings{dotson_optimal_2020-1,
	address = {Phoenix, AZ},
	series = {Reactor {Physics} of {Micro} {Reactors} for {Terrestrial} and {Space} {Applications}{\textemdash}{II}},
	title = {Optimal {Sizing} of a {Micro}-reactor for {Embedded} {Grid} {Systems}},
	volume = {122},
	url = {https://youtu.be/Z36xWxW0FNk},
	doi = {http://epubs.ans.org/?a=48333},
	abstract = {There has been significant work recently to develop en- ergy system concepts that incorporate a mixture of nuclear energy, variable renewable energy (VRE) and energy storage techniques. These systems are often referred to as nuclear hy- brid energy systems (NHES) and are generally robust, reliable, economically appealing, and have low to zero greenhouse gas (GHG) emissions [1, 2, 3, 4]. In 2015, the University of Illi- nois at Urbana-Champaign (UIUC) made a commitment to reach carbon neutrality by 2050 in the Illinois Climate Ac- tion Plan (iCAP) [5]. This plan identified nuclear energy as a potential contributor to this goal. In this work we use the RAVEN framework to find the optimal size for a micro-reactor that would minimize the levelized cost of electricity (LCOE) for the UIUC embedded grid. The greatest source economic variability is contained in the capital costs of a micro-reactor. Thus we examine both scenarios where the reactor is provided at no cost to the university and purchased at full price.},
	language = {en},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Annual} {Meeting}},
	publisher = {American Nuclear Society},
	author = {Dotson, Samuel G. and Huff, Kathryn D.},
	month = jun,
	year = {2020},
	pages = {682--685},
	file = {Dotson and Huff - 2020 - Optimal Sizing of a Micro-reactor for Embedded Gri.pdf:/Users/huff/Zotero/storage/6GA7KQ62/Dotson and Huff - 2020 - Optimal Sizing of a Micro-reactor for Embedded Gri.pdf:application/pdf},
}

@inproceedings{fairhurst_agosta_hydrogen_2020,
	address = {Raleigh, NC},
	title = {Hydrogen {Economy} in {Champaign}-{Urbana}, {IL}},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Student} {Conference}},
	publisher = {American Nuclear Society},
	author = {Fairhurst Agosta, Roberto and Dotson, Samuel and Huff, Kathryn},
	month = mar,
	year = {2020},
	file = {Fairhurst Agosta et al. - 2020 - Hydrogen Economy in Champaign-Urbana, IL.pdf:/Users/huff/Zotero/storage/3B4B9NS6/Fairhurst Agosta et al. - 2020 - Hydrogen Economy in Champaign-Urbana, IL.pdf:application/pdf},
}

@inproceedings{fairhurst_agosta_hydrogen_2020-1,
	address = {Phoenix, AZ},
	series = {General {Topics} in {Decommissioning}},
	title = {Hydrogen {Economy} in {Champaign}-{Urbana}, {IL}},
	volume = {122},
	url = {http://epubs.ans.org/?a=48167},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Annual} {Meeting}},
	publisher = {American Nuclear Society},
	author = {Fairhurst Agosta, Roberto and Dotson, Samuel and Huff, Kathryn},
	month = jun,
	year = {2020},
	file = {Fairhurst Agosta et al. - 2020 - Hydrogen Economy in Champaign-Urbana, IL.pdf:/Users/huff/Zotero/storage/QR3RJ9Y9/Fairhurst Agosta et al. - 2020 - Hydrogen Economy in Champaign-Urbana, IL.pdf:application/pdf},
}

@misc{white_331_2020,
	address = {Embedded.fm},
	title = {331: {Friendly} {Tea} {Kettle}},
	copyright = {License: CC-A-NC-ND},
	shorttitle = {331},
	url = {https://embedded.fm/episodes/331},
	abstract = {Dr. Katy Huff  (@katyhuff)  spoke with us about nuclear engineering, effective software development, and the apropos command.  Katy wrote an O{\textquoteright}Reilly book describing Python software development to scientists:  Effective Computation in Physics: Field Guide to Research with Python . She has been invol},
	language = {en-US},
	urldate = {2020-05-22},
	journal = {Embedded Podcast},
	publisher = {Embedded.fm},
	author = {White, Elecia and White, Christopher},
	collaborator = {Huff, Kathryn D.},
	month = may,
	year = {2020},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/EVY67YTW/331.html:text/html},
}

@article{miernicki_nuclear_2020,
	title = {Nuclear waste heat use in agriculture: {History} and opportunities in the {United} {States}},
	volume = {267},
	issn = {0959-6526},
	shorttitle = {Nuclear waste heat use in agriculture},
	url = {http://www.sciencedirect.com/science/article/pii/S095965262031965X},
	doi = {10.1016/j.jclepro.2020.121918},
	abstract = {Nuclear power plants (NPPs) produce a large amount of waste heat (WH) that has generally been perceived and regulated as an environmental liability. Given the abundance of WH from NPPs and the ubiquity of generally low-grade heat requirements of agricultural operations, from production to post-harvest, there is remarkable potential to harness NPP WH for agricultural uses with mutual economic advantages to NPPs and agricultural sectors. Taking advantage of this WH resource may improve the financial outlook of both the partnered power plants and agricultural businesses by providing an additional revenue stream, decreased heating costs, and a reduced carbon footprint. This review summarizes and interprets the historical discourse and research on agricultural applications of NPP WH in the U.S., and synthesizes technical constraints, unknowns, and opportunities for realizing the benefits of WH derived from the nuclear energy sector for agricultural value chains. Previous applications of WH in the agricultural industry demonstrate that this is a viable option to the benefit of the parties involved under the right conditions, but relatively little has been done to further this technology in the U.S. in recent years or explore novel applications. A revival of interest in this technology may be warranted given the current outlook for NPPs in the U.S. and a general interest in reducing the environmental impact of agriculture.},
	language = {en},
	urldate = {2020-06-03},
	journal = {Journal of Cleaner Production},
	author = {Miernicki, Elizabeth A. and Heald, Alexander L. and Huff, Kathryn D. and Brooks, Caleb S. and Margenot, Andrew J.},
	month = sep,
	year = {2020},
	pages = {121918},
	file = {Elizabeth A. Miernicki et al. - 2019 - Nuclear waste heat use in agriculture history and.pdf:/Users/huff/Zotero/storage/ABSAF3SA/Elizabeth A. Miernicki et al. - 2019 - Nuclear waste heat use in agriculture history and.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/A89NY9G3/Miernicki et al. - 2020 - Nuclear waste heat use in agriculture History and.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/ETHXEJLI/S095965262031965X.html:text/html},
}

@inproceedings{turkmen_single_2020,
	address = {Virtual Meeting},
	series = {Virtual {Conference}},
	title = {Single {Channel} {Design} {Based} on {Artificial} {Intelligence} for {Molten} {Salt} {Reactors}},
	volume = {122},
	url = {http://epubs.ans.org/?a=48340},
	abstract = {Aim:
To introduce an efficient, novel, robust, accelerated and reliable design recommendation approach based on
machine learning methods in predicting performance metrics of any design
Why:
- parametric studies ignore interdependence of variables
- obligation to use a reactor physics code for any neutron transport calculation
- possibility to converge to a local instead of global optima
- concerns on the parameters of the optimizers due to the indeterminacy of these parameters prior to
evaluations},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Turkmen, Mehmet and Huff, Kathryn D},
	month = jun,
	year = {2020},
	pages = {712--713},
	file = {ANS_Annual_Meeting_2020_Presentation.pdf:/Users/huff/Zotero/storage/XQ5ERDST/ANS_Annual_Meeting_2020_Presentation.pdf:application/pdf;Turkmen and Huff - 2020 - Single Channel Design Based on Artificial Intellig.pdf:/Users/huff/Zotero/storage/87FMCJ5K/Turkmen and Huff - 2020 - Single Channel Design Based on Artificial Intellig.pdf:application/pdf},
}

@misc{dotson_optimal_2020-2,
	address = {Online Virtual Meeting},
	type = {Technical {Presentation}},
	title = {Optimal {Sizing} of a {Micro}-reactor for {Embedded} {Grid} {Systems}},
	abstract = {In 2015, the University of Illinois at Urbana-Champaign (UIUC) made a commitment to reach carbon neutrality by 2050 in the Illinois Climate Action Plan (iCAP) 
This plan identified nuclear energy as a potential contributor to this goal.
In this work, we use the Temoa framework to find the optimal size for a micro-reactor that would minimize the levelized cost of electricity (LCOE) for the UIUC embedded grid.
The greatest source of economic variability is contained in the capital costs of a micro-reactor. Thus we examine both scenarios where the reactor is provided at no cost to the university and purchased at full price.},
	language = {en},
	author = {Dotson, Samuel G.},
	month = jun,
	year = {2020},
	file = {Dotson - 2020 - Optimal Sizing of a Micro-reactor for Embedded Gri.pdf:/Users/huff/Zotero/storage/CU2LZ5CY/Dotson - 2020 - Optimal Sizing of a Micro-reactor for Embedded Gri.pdf:application/pdf},
}

@phdthesis{rykhlevskii_fuel_2018,
	address = {Urbana, IL},
	type = {Prelim},
	title = {Fuel {Processing} {Simulation} {Tool} for {Liquid}-fueled {Nuclear} {Reactors}},
	copyright = {Copyright 2019 Andrei Rykhlevskii},
	abstract = {In the search for new ways to generate carbon-free, reliable base-load power, interest in advanced nuclear energy technologies, particularly Molten Salt Reactors (MSRs), has resurged with multiple new companies pursuing MSR commercialization. To further develop these MSR concepts, researchers need simulation tools for analyzing liquid-fueled MSR depletion and fuel processing. Current MSR modeling efforts in the literature usually assume ideal (e.g., 100\% of neutron poison being removed) rather than realistically constrained removal efficiency. This work proposes to create a Python package, SaltProc, which will implement realistically constrained extraction efficiency of fission product based on physical models of fuel processing components appearing in various MSR systems. To demonstrate the capabilities of SaltProc, the Transatomic Power (TAP) concept will be simulated to capture the evolution of fuel salt composition during reactor operation with a realistic, physics-driven model of an online fuel reprocessing system. SaltProc will also be applied to determine the feasibility and safety of load following for the TAP system. This proposal outlines extensions to this work, including investigating safety parameters (temperature coefficients, shutdown margin, axial power offset) evolution over a 60-year reactor operation lifetime and during short-term load-following transients.},
	school = {University of Illinois at Urbana-Champaign},
	author = {Rykhlevskii, Andrei},
	month = apr,
	year = {2018},
	file = {Prelim Document:/Users/huff/Zotero/storage/M3TSQR4M/Rykhlevskii - 2018 - Fuel Processing Simulation Tool for Liquid-fueled .pdf:application/pdf;Prelim Presentation:/Users/huff/Zotero/storage/9EHLBWEK/prelim_presentation.pdf:application/pdf},
}

@phdthesis{rykhlevskii_fuel_2020,
	address = {Urbana, IL},
	type = {Doctoral {Dissertation}},
	title = {Fuel {Processing} {Simulation} {Tool} for {Liquid}-fueled {Nuclear} {Reactors}},
	copyright = {Copyright 2020 Andrei Rykhlevskii},
	url = {http://hdl.handle.net/2142/108460},
	language = {English},
	school = {University of Illinois at Urbana-Champaign},
	author = {Rykhlevskii, Andrei},
	month = jul,
	year = {2020},
	file = {Dissertation:/Users/huff/Zotero/storage/27V6UCA7/Rykhlevskii - 2020 - Fuel Processing Simulation Tool for Liquid-fueled .pdf:application/pdf;Presentation:/Users/huff/Zotero/storage/KU5RAWWI/defense_presentation.pdf:application/pdf},
}

@phdthesis{erik_andrew_medhurst_photogrammetry_2020,
	address = {Urbana, IL},
	type = {{MS} {Nuclear} {Engineering} and {Engineering} {Physics}},
	title = {Photogrammetry, {Cloud} {Storage}, {Virtual} {Reality}, and {Augmented} {Reality} to {Guide} {Radiation} {Measurement} {Planning} and {Visualization} {PROCESS}},
	abstract = {Localizing a radiation source in an urban environment is a challenge in nuclear nonproliferation
and radiation detection. One approach to localize a source is to send a mobile radiation sensor
network into an area of interest to collect count rate measurements at many locations in an
attempt to find the radiation source. However, there are numerous temporal and spatial factors
that cause changes in background count rate measurements, and these factors make it challenging
to analyze the collected data. Displaying these measurements in a virtual environment has
contextualized them and helps a user determine if environmental factors are introducing false
positives. A virtual model has been shown to visualize collected measurements in near real-time,
but not in real-time. The ability for a user to quickly address alarm measurements is hampered
by this lack of real-time data access as well as due to poor quality virtual models.
Another challenge in radiation detection is sampling an environment to assess the status of an
area following a radiological or nuclear incident. Following an incident, environmental samples
must be collected and analyzed to identify the radioactive substances present and assess the
environmental damages. Incident response must be rapid and the sample collection must occur
without error. A software named Visual Sample Plan (VSP) has been developed by Pacific
Northwest National Laboratory (PNNL) to help guide the sample collection process and
statistically inform decisions. This thesis begins with an overview of the radiation source search
and environmental sampling problems and how they have been addressed. Next, earlier work that
has attempted to address each of these problems and the motivation for these responses is
discussed. Finally, new work extending the prior solutions is discussed. To address the radiation
source search problem, a method to create higher quality 3D models is explored, and an alternate
method to store and retrieve data in the cloud using DynamoDB is implemented. By
implementing VSP in Augmented Reality (AR), opportunities for error are further limited. This
thesis concludes with suggestions for future work to approach robust solutions to each problem.},
	school = {University of Illinois at Urbana-Champaign},
	author = {{Erik Andrew Medhurst}},
	month = may,
	year = {2020},
}

@article{chee_demand-driven_2020,
	title = {Demand-{Driven} {Deployment} {Capabilities} in {Cyclus}, a {Fuel} {Cycle} {Simulator}},
	volume = {0},
	issn = {0029-5450},
	url = {https://doi.org/10.1080/00295450.2020.1753444},
	doi = {10.1080/00295450.2020.1753444},
	abstract = {The present U.S. nuclear fuel cycle faces challenges that hinder the expansion of nuclear energy technology. The U.S. Department of Energy identified four nuclear fuel cycle options that make nuclear energy technology more desirable. Successfully analyzing the transitions from the current fuel cycle to these promising fuel cycles requires a nuclear fuel cycle simulator that can predictively and automatically deploy fuel cycle facilities to meet user-defined power demand. This work introduces and demonstrates the demand-driven deployment capabilities in Cyclus, an open-source nuclear fuel cycle simulator framework. User-controlled capabilities such as time-series forecasting algorithms, supply buffers, and facility preferences were introduced to give users tools to minimize power undersupply in a transition scenario simulation. The demand-driven deployment capabilities are referred to as d3ploy. We demonstrate the capability of d3ploy to predict future commodities{\textquoteright} supply and demand, and automatically deploy fuel cycle facilities to meet the predicted demand in four transition scenarios. Using d3ploy to set up transition scenarios saves the user simulation setup time compared to previous efforts that required a user to manually calculate and use trial and error to set up the deployment scheme for the supporting fuel cycle facilities.},
	number = {0},
	urldate = {2020-08-07},
	journal = {Nuclear Technology},
	author = {Chee, Gwendolyn J. and Agosta, Roberto E. Fairhurst and Bae, Jin Whan and Flanagan, Robert R. and Scopatz, Anthony M. and Huff, Kathryn D.},
	month = jul,
	year = {2020},
	keywords = {nuclear fuel cycle, Nuclear engineering, automated deployment, nuclear fuel cycle simulator, time-series forecasting},
	pages = {1--22},
	file = {Chee et al. - 2020 - Demand Driven Deployment Capabilities in Cyclus, a.pdf:/Users/huff/Zotero/storage/WK7485EH/Chee et al. - 2020 - Demand Driven Deployment Capabilities in Cyclus, a.pdf:application/pdf;Full Text PDF:/Users/huff/Zotero/storage/G6HF87WZ/G6HF87WZ.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/987KXZR2/00295450.2020.html:text/html},
}

@article{ashraf_strategies_2020,
	title = {Strategies for thorium fuel cycle transition in the {SD}-{TMSR}},
	volume = {148},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454920303546},
	doi = {10.1016/j.anucene.2020.107656},
	abstract = {Liquid-fueled Molten Salt Reactor (MSR) systems represent advances in safety, economics, and sustainability. The MSR has been designed to operate with a Th/233U fuel cycle with 233U used as startup fissile material. Since 233U does not exist in nature, we must examine other available fissile materials to start up these reactor concepts. This work investigates the fuel cycle and neutronics performance of the Single-fluid Double-zone Thorium-based Molten Salt Reactor (SD-TMSR) with different fissile material loadings at startup: High Assay Low Enriched Uranium (HALEU) (19.79\%), Pu mixed with HALEU (19.79\%), reactor-grade Pu (a mixture of Pu isotopes chemically extracted from Pressurized Water Reactor (PWR) spent nuclear fuel (SNF) with 33 GWd/tHM burnup), transuranic elements (TRU) from Light Water Reactor (LWR) SNF, and 233U. The MSR burnup routine provided by SERPENT-2 is used to simulate the online reprocessing and refueling in the SD-TMSR. The effective multiplication factor, fuel salt composition evolution, and net production of 233U are studied in the present work. Additionally, the neutron spectrum shift during the reactor operation is calculated. The results show that the continuous flow of reactor-grade Pu helps transition to the thorium fuel cycle within a relatively short time (?4.5 years) compared to 26~years for 233U startup fuel. Finally, using TRU as the initial fuel materials offers the possibility of operating the SD-TMSR for an extended period of time (?40~years) without any external feed of 233U.},
	language = {en},
	urldate = {2020-08-07},
	journal = {Annals of Nuclear Energy},
	author = {Ashraf, O. and Rykhlevskii, Andrei and Tikhomirov, G. V. and Huff, Kathryn D.},
	month = dec,
	year = {2020},
	keywords = {Burnup, Online reprocessing, MSR, Thorium fuel cycle, Breeding reactor, Monte carlo code, Burner, Transuranic},
	pages = {107656},
	file = {Ashraf et al. - 2020 - Strategies for thorium fuel cycle transition in th.pdf:/Users/huff/Zotero/storage/35RLINR8/Ashraf et al. - 2020 - Strategies for thorium fuel cycle transition in th.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/LNE4XGGP/S0306454920303546.html:text/html;ScienceDirect Snapshot:/Users/huff/Zotero/storage/IMSNNMIB/S0306454920303546.html:text/html},
}

@mastersthesis{park_advancement_2020,
	address = {Urbana, IL},
	title = {Advancement and {Verification} of {Moltres} for {Molten} {Salt} {Reactor} {Safety} {Analysis}},
	copyright = {Copyright 2020 Sun Myung Park},
	url = {https://www.ideals.illinois.edu/handle/2142/108542},
	language = {English},
	school = {University of Illinois at Urbana-Champaign},
	author = {Park, Sun Myung},
	month = aug,
	year = {2020},
	file = {Park - 2020 - Advancement and Verification of Moltres for Molten.pdf:/Users/huff/Zotero/storage/JYYYTBJ7/Park - 2020 - Advancement and Verification of Moltres for Molten.pdf:application/pdf},
}

@article{chaube_role_2020,
	title = {The {Role} of {Hydrogen} in {Achieving} {Long} {Term} {Japanese} {Energy} {System} {Goals}},
	volume = {13},
	copyright = {http://creativecommons.org/licenses/by/3.0/},
	url = {https://www.mdpi.com/1996-1073/13/17/4539},
	doi = {10.3390/en13174539},
	abstract = {This research qualitatively reviews literature regarding energy system modeling in Japan specific to the future hydrogen economy, leveraging quantitative model outcomes to establish the potential future deployment of hydrogen in Japan. The analysis focuses on the four key sectors of storage, supplementing the gas grid, power generation, and transportation, detailing the potential range of hydrogen technologies which are expected to penetrate Japanese energy markets up to 2050 and beyond. Alongside key model outcomes, the appropriate policy settings, governance and market mechanisms are described which underpin the potential hydrogen economy future for Japan. We find that transportation, gas grid supplementation, and storage end-uses may emerge in significant quantities due to policies which encourage ambitious implementation targets, investment in technologies and research and development, and the emergence of a future carbon pricing regime. On the other hand, for Japan which will initially be dependent on imported hydrogen, the cost of imports appears critical to the emergence of broad hydrogen usage, particularly in the power generation sector. Further, the consideration of demographics in Japan, recognizing the aging, shrinking population and peoples\’ energy use preferences will likely be instrumental in realizing a smooth transition toward a hydrogen economy.},
	language = {en},
	number = {17},
	urldate = {2020-09-02},
	journal = {Energies},
	author = {Chaube, Anshuman and Chapman, Andrew and Shigetomi, Yosuke and Huff, Kathryn and Stubbins, James},
	month = sep,
	year = {2020},
	note = {Number: 17
Publisher: Multidisciplinary Digital Publishing Institute},
	keywords = {Japan, sustainability, energy model, fuel cell, hydrogen economy},
	pages = {4539},
	file = {Full Text PDF:/Users/huff/Zotero/storage/UTQTDZUG/Chaube et al. - 2020 - The Role of Hydrogen in Achieving Long Term Japane.pdf:application/pdf;Full Text PDF:/Users/huff/Zotero/storage/MMKN58DL/Chaube et al. - 2020 - The Role of Hydrogen in Achieving Long Term Japane.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/YE28USUH/htm.html:text/html;Snapshot:/Users/huff/Zotero/storage/8TCX8L67/4539.html:text/html},
}

@techreport{lee_milestone_2020,
	address = {Urbana, IL},
	type = {Milestone {Report}},
	title = {Milestone 3.2 {Report}: {Thermal}-{Hydraulics} {Analysis} of {Core} {LoadFollowing} {Operation}},
	shorttitle = {Contract {DE}-{AR0000983}, {Enabling} {Load} {Following} {Capability} in the {Transatomic} {MSR}},
	abstract = {The University of Illinois, Urbana-Champaign (UIUC) is engaged in work to develop a fuel processing system that enables load-following in Molten Salt Reactors (MSRs), an important ability that allows nuclear power plants to ramp electricity production up or down to meet changing electricity demand. Nuclear reactions in MSRs produce unwanted byproducts (such as xenon and krypton) that can adversely affect power production. In steady, baseload operation, these byproducts form and decay at the same rate. When electricity production is ramped down, however, the byproducts start to be produced at a greater rate than they decay, leading to a buildup within the reactor. When power production must be once again increased, the response rate is slowed by the time needed for the byproducts to reach their equilibrium level (determined by the radioactive decay half-life, which is on the order of hours). Thus, buildup of these unwanted byproducts resulting from ramping down inhibit proper load following for molten salt reactors. Fortunately, MSRs transport fuel in a flowing molten salt fuel loop, which means that a section of the reactor, outside the core, can be leveraged for fuel processing and "cleanup." The team will determine the feasibility of removal of these unwanted byproducts and de- sign a fuel reprocessing system, removing a major barrier to commercialization for molten salt reactors.

The University of Illinois, Urbana-Champaign (UIUC) performed a study in August 2019 to analyze the
neutronics behavior of the Transatomic Power Molten Salt Reactor (TAP MSR) core during
loadfollowing operations, culminating in the Milestone 3.1 Report [1] . As a follow-up to the previous
work, we will be analyzing the thermal-hydraulics behavior of the TAP MSR in this work.},
	language = {english},
	number = {UIUC-ARTS-2020-08},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Lee, Alvin J.H. and Kozlowksi, Tomasz and Huff, Kathryn},
	month = aug,
	year = {2020},
	keywords = {cyclus, nuclear engineering, arfc, report, molten salt reactor, nuclear fuel cycle},
	pages = {1--20},
	file = {Meitner Milestone 3.2_FinalDraft (1).docx:/Users/huff/Zotero/storage/CK7LEQ87/Meitner Milestone 3.2_FinalDraft (1).docx:application/vnd.openxmlformats-officedocument.wordprocessingml.document;Meitner Milestone 3.2_FinalDraft.pdf:/Users/huff/Zotero/storage/HQILK7BT/Meitner Milestone 3.2_FinalDraft.pdf:application/pdf},
}

@misc{bushak_university_2020,
	title = {University {Of} {Illinois} {Proposes} {Micronuclear} {Reactor} {To} {Cut} {Carbon} {Emissions} -},
	url = {https://illinoisnewsroom.org/university-of-illinois-proposes-micronuclear-reactor-to-cut-carbon-emissions/},
	abstract = {URBANA {\textemdash} University of Illinois researchers have proposed investing in a micronuclear reactor to help fight carbon emissions{\textemdash}and reach a goal of making the Urbana-Champaign campus carbon neutral by 2050. The proposed micronuclear reactor would contribute about 13\% of campus energy and help reduce the university{\textquoteright}s carbon footprint. The proposal is being submitted to the [{\textellipsis}]},
	language = {en-US},
	urldate = {2020-10-12},
	author = {Bushak, Lecia},
	month = sep,
	year = {2020},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/Z58NSWEZ/university-of-illinois-proposes-micronuclear-reactor-to-cut-carbon-emissions.html:text/html},
}

@misc{dotson_future_2020,
	address = {Highland Park, IL},
	type = {Invited {Talk}},
	title = {The {Future} of {Nuclear} {Energy}},
	url = {https://youtu.be/TY0_yvAC5Xg},
	abstract = {uclear energy has to the potential to promote peace by enabling the decommissioning of nuclear weapons and societies can leverage nuclear's zero emissions electricity to fully decarbonize their electric grids for a green future.},
	language = {en},
	author = {Dotson, Samuel G.},
	month = oct,
	year = {2020},
	file = {Dotson - 2020 - The Future of Nuclear Energy.pdf:/Users/huff/Zotero/storage/QYL3XEYS/Dotson - 2020 - The Future of Nuclear Energy.pdf:application/pdf},
}

@article{ans_day_2020,
	title = {A {Day} in the {Life} of the {Nuclear} {Community}},
	volume = {63},
	issn = {0029-5574},
	shorttitle = {The {People} of {Nuclear}},
	url = {https://www.ans.org/pubs/magazines/download/article-1221/},
	abstract = {This issue of Nuclear News is focused on the individuals who make up our nuclear community.
We invited a small group of those individuals to tell us about their day-to-day work in some of the many occupations and applications of nuclear science and technology, and they responded generously. They were ready to tell us about the part they play, togeth- er with colleagues and team members, in supplying clean energy, advancing technology, protecting safety and health, and exploring fundamental science.
In these pages, we see a community that can cele- brate both those workdays that record progress mov- ing at a steady pace and the exceptional days when a goal is reached, a briefing is delivered, a contract goes through, a discovery is made, or an unforeseen chal- lenge is overcome.
The Nuclear News staff hopes that you enjoy meet- ing these members of our community{\textemdash}or maybe get reacquainted with friends{\textemdash}through their words and photos.},
	language = {english},
	number = {12},
	urldate = {2020-11-06},
	journal = {Nuclear News},
	author = {{ANS}},
	collaborator = {Huff, Kathryn},
	month = nov,
	year = {2020},
	note = {media},
	pages = {23--37},
	file = {Huff - 2020 - A Day in the Life of the Nuclear Community.pdf:/Users/huff/Zotero/storage/ZQDB9758/Huff - 2020 - A Day in the Life of the Nuclear Community.pdf:application/pdf;Nuclear News -- ANS / Publications / Magazines:/Users/huff/Zotero/storage/PT5FYUFD/nn.html:text/html},
}

@article{robinson_university_2020,
	address = {Urbana, IL},
	chapter = {Around Campus},
	edition = {September 14, 2020},
	title = {University awaits approval for on-campus micro-nuclear reactor},
	url = {https://dailyillini.com/news/2020/09/14/university-awaits-approval-for-micronuclear-reactor/},
	abstract = {The University may soon be home to a new micro-nuclear reactor, which would provide campus with clean energy, as well as opportunities in research and education on campus.~ The project is pending approval and funding by the U.S. Department of Energy. If awarded, work will begin in 2021, with projected completion by 2026.~ The DOE...},
	language = {en, sv},
	urldate = {2020-11-06},
	journal = {The Daily Illini - The Independent Student Newspaper at the University of Illinois},
	author = {Robinson, Heather},
	collaborator = {Huff, Kathryn},
	month = sep,
	year = {2020},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/F3JF55PV/university-awaits-approval-for-micronuclear-reactor.html:text/html},
}

@article{bohannon_female_2016,
	title = {Female engineers publish in better journals, but receive fewer citations},
	volume = {Scientific Community},
	url = {https://www.sciencemag.org/news/2016/01/female-engineers-publish-better-journals-receive-fewer-citations},
	abstract = {An analysis of co-authors on engineering papers finds that these differences are tiny},
	language = {en},
	number = {doi:10.1126/science.aae0191},
	urldate = {2020-11-06},
	journal = {Science {\textbar} AAAS},
	author = {Bohannon, John},
	month = jan,
	year = {2016},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/WNFC2JNE/female-engineers-publish-better-journals-receive-fewer-citations.html:text/html},
}

@inproceedings{scopatz_modernizing_2015,
	address = {Washington, D.C.},
	series = {Education and {Training}: {General}{\textemdash}{II}},
	title = {Modernizing {Computational} {Nuclear} {Engineering} {Education} in the {Open}},
	volume = {113},
	url = {http://epubs.ans.org/?a=37748},
	urldate = {2020-11-10},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	author = {Scopatz, Anthony M and Huff, Kathryn D.},
	month = nov,
	year = {2015},
	pages = {111--114},
	file = {ANS / Digital Nuclear Library / Transactions / Volume 113 / Number 1 / Pages 111-114:/Users/huff/Zotero/storage/ZN7UYT6K/epubs.ans.org.html:text/html;Scopatz and Huff - 2015 - Modernizing Computational Nuclear Engineering Educ.pdf:/Users/huff/Zotero/storage/QRQTFZ9S/Scopatz and Huff - 2015 - Modernizing Computational Nuclear Engineering Educ.pdf:application/pdf},
}

@misc{huff_workforce_2017,
	address = {San Francisco, CA},
	type = {Panel},
	title = {Workforce {Transition}: {How} to {Succeed}-{Panel}},
	url = {http://epubs.ans.org/?a=40958},
	author = {Huff, Kathryn D.},
	month = jun,
	year = {2017},
}

@inproceedings{huff_current_2016,
	address = {Washington D.C.},
	series = {Mathematics and {Computation}},
	title = {Current {Issues} in {Computational} {Methods}-{Roundtable}},
	volume = {115},
	url = {http://epubs.ans.org/?a=39205},
	abstract = {But I just want to write software?
The details can feel overwhelming and stifling in pursuit of writing high-impact, high-quality software: intellectual property, li- censing, copyright, export control, open source, access on clusters... All of this can deeply impact how accessible your work is. Our panel members will share lessons-learned and experiences in the legal realm, with an emphasis on highly collaborative software development involving multiple institutions.
Panelists: Kevin Clarno (ORNL) Rich Martineau (INL)
Kathryn Huff (Univ of Illinois, Urbana-Champaign) Kathleen McDonald (LANL)},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Winter} {Meeting}},
	publisher = {Amer Nuclear Society},
	author = {Huff, Kathryn D. and Martineau, Richard and McDonald, Kathleen and Clarno, Kevin},
	collaborator = {Slaybaugh, Rachel N.},
	month = nov,
	year = {2016},
	pages = {487},
}

@article{schuler_ans_2017,
	title = {{ANS} {Annual} {Meeting}: {Education}, {Training}, and {Workforce} {Development}: {Transitioning} to the workforce},
	volume = {60},
	issn = {0029-5574)},
	shorttitle = {Transitioning to the {Workforce}},
	url = {http://epubs.ans.org/download/?i=2141},
	abstract = {ANS{\textquoteright}s Young Members Group sponsored a session at which attendees had the opportunity to learn from the experiences of a panel
of young professionals.},
	language = {english},
	number = {9},
	urldate = {2020-11-06},
	journal = {Nuclear News},
	author = {Schuler, Kaitlin},
	month = aug,
	year = {2017},
	note = {media},
	pages = {127--128},
	file = {Schuler - 2017 - 2017 ANS Annual Meeting Education, Training, and .pdf:/Users/huff/Zotero/storage/ZXVG99GT/Schuler - 2017 - 2017 ANS Annual Meeting Education, Training, and .pdf:application/pdf},
}

@inproceedings{taylor_experiences_2013,
	address = {Atlanta, GA},
	series = {Professional {Women} in {ANS}},
	title = {Experiences of {Women} in {Nuclear}-{Panel}},
	volume = {108},
	url = {http://epubs.ans.org/?a=16495},
	abstract = {The Professional Women in ANS proposes a panel session for all attendees of the 2013 ANS annual conference. For this panel, women in three varying stages of their careers will be invited to share their experiences with the gathering. A mature student, a mid-career individual, and an experi- enced professional will speak of their career choices, challenges encountered, and their roles in the nuclear field. This panel will help bring out the subtle differences in professional experiences for men and women in nuclear and will encourage all members of ANS to learn from and relate to them.},
	language = {en},
	booktitle = {Transactions of the {American} {Nuclear} {Soceity} {Annual} {Meeting}},
	publisher = {American Nuclear Society},
	author = {Briggs, Laural and Huff, Katy and Hansen, Linda},
	collaborator = {Taylor, J'Tia},
	month = jun,
	year = {2013},
	pages = {49},
	file = {ANS / Digital Nuclear Library / Transactions / Volume 108 / Number 1 / Page 49:/Users/huff/Zotero/storage/BCMWHMV9/epubs.ans.org.html:text/html;Briggs et al. - Panelists Mary Lou Dunzik-Gougar (Idaho State Univ.pdf:/Users/huff/Zotero/storage/IMWPICVS/Briggs et al. - Panelists Mary Lou Dunzik-Gougar (Idaho State Univ.pdf:application/pdf},
}

@inproceedings{huff_strategy_2018,
	address = {Orlando, FL},
	series = {Education, {Training}, and {Workforce} {Development}},
	title = {Strategy {Development} for {Junior} {Faculty}-{Panel}},
	volume = {119},
	url = {http://epubs.ans.org/?a=44153},
	abstract = {This panel discussion will address topics important to junior and tenure-track faculty members including course development strate- gies, student mentoring and development, proposal writing, and tenure package preparation among other topics. The panel will be com- posed of one senior faculty member, to moderate discussion and provide input, and three junior faculty members or recently tenured professors that will spur discussion on topics of importance to faculty members during their early academic careers. The panel will be focused on facilitating robust discussions with attendees to create a space for junior faculty members to come together as a community.},
	language = {en},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Huff, Kathryn D. and Roberts, Jeremy and Allen, Todd and Aitkaliyeva, Assel},
	collaborator = {Thomas, Andrew E.},
	month = nov,
	year = {2018},
	pages = {71},
	file = {Huff and Roberts - Panelists Todd Allen (Univ of Wisconsin, Madison).pdf:/Users/huff/Zotero/storage/KTD89KHN/Huff and Roberts - Panelists Todd Allen (Univ of Wisconsin, Madison).pdf:application/pdf},
}

@inproceedings{huff_current_2017-1,
	address = {San Francisco, CA},
	series = {Mathematics and {Computation}},
	title = {Current {Issues} in {Computational} {Methods}-{Roundtable}},
	volume = {116},
	url = {http://epubs.ans.org/?a=40674},
	abstract = {But Can You Remake That Plot (and Can Anyone Else)?
Reproducible, Transparent, and Open Computation in Nuclear Engineering
How reproducible is the science involving data and computation? Is something science if it{\textquoteright}s not reproducible? Nuclear, more than many fields, has a burden to do science responsibly. This includes setting up reproducible, transparent workflows for computation. This panel of experts will discuss associated strategies, motivations, best practices, and challenges.
A challenge that is especially true for nuclear is the relationship between openness and reproducibility. Our software, data, and models often come with restrictions-making it difficult to share our work in a way that makes it verifiable by independent researchers. This panel will also investigate how to manage scientific integrity in conjunction with legal restrictions in nuclear computation.},
	booktitle = {Transactions of the {American} {Nuclear} {Society} {Annual} {Meeting}},
	publisher = {Amer Nuclear Society},
	author = {Huff, Kathryn D. and White, Morgan and Deniz, Fatma and Frenklach, Michael and Johnson, Seth and Slaybaugh, Rachel N.},
	month = jun,
	year = {2017},
	pages = {529},
}

@techreport{huff_demand_2019-1,
	address = {Urbana, IL},
	type = {Final {Technical} {Report}},
	title = {Demand {Driven} {Cycamore} {Archetypes} - {NEUP} {Final} {Technical} {Report}},
	url = {https://www.osti.gov/biblio/1594895},
	abstract = {The U.S. Department of Energy's Office of Scientific and Technical Information},
	language = {English},
	number = {UIUC-USC-2020-01},
	urldate = {2020-11-12},
	institution = {University of Illinois at Urbana-Champaign; Univ. of South Carolina, Columbia, SC (United States)},
	author = {Huff, Kathryn D. and Knight, Travis W.},
	collaborator = {Bae, Jin Whan and Bhosale, Aditya and Chandan, Snehal and Chee, Gwendolyn J. and Fairhurst, Roberto E. and Flanagan, Robert R. and Kissinger, Louis and Park, Gyutae and Scopatz, Anthony M.},
	month = dec,
	year = {2019},
	doi = {10.2172/1594895},
	pages = {1--37},
	file = {Full Text PDF:/Users/huff/Zotero/storage/XLARJ4EH/Huff and Knight - 2019 - Demand Driven Cycamore Archetypes.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/E4LKHTYH/1594895.html:text/html;Snapshot:/Users/huff/Zotero/storage/38UNYM8C/1594895.html:text/html},
}

@misc{huff_effective_2020,
	address = {Virtual Seminar},
	type = {Webinar},
	title = {Effective {Writing} {From} {Home} with {Dr}. {Katy} {Huff}},
	shorttitle = {http://gradswe.swe.org/},
	url = {https://katyhuff.github.io/2020-05-20-writing/#/},
	author = {Huff, Kathryn D.},
	month = may,
	year = {2020},
}

@misc{huff_microreactor_2020,
	address = {Washington, DC (virtual)},
	type = {Invited {Panel}},
	title = {Microreactor {Customer} {Perspective} {\textendash} {Panel} {Discussion}},
	url = {https://gain.inl.gov/GAINEPRINEI_MicroreactorProgramVirtualWorkshopPres/00-MicroreactorVirtualWkshpAgenda,18Aug2020.pdf},
	author = {Huff, Kathryn D. and Brooks, Caleb S.},
	month = aug,
	year = {2020},
	file = {Huff and Brooks - 2020 - Microreactor Customer Perspective {\textendash} Panel Discussi.pdf:/Users/huff/Zotero/storage/KQ7U9IN7/Huff and Brooks - 2020 - Microreactor Customer Perspective {\textendash} Panel Discussi.pdf:application/pdf},
}

@inproceedings{smith_introducing_2017,
	address = {Austin, TX, United States},
	title = {Introducing {JOSS}: {The} {Journal} of {Open} {Source} {Software}},
	shorttitle = {Introducing {JOSS}},
	doi = {10.6084/m9.figshare.5208151.v1},
	abstract = {Talk presented at the 2017 Python in Science Conference (SciPy), on 13 July 2017 in Austin, TX.AbstractThis talk describes the motivation and progress of the Journal of Open Source Software (JOSS), a free, open-access journal designed to publish brief articles about research software. The primary purpose of JOSS is to enable developers of research software to receive citation credit equivalent to typical archival publications. Rather than a review of a lengthy software paper (including, e.g., methodology, validation, sample results), JOSS submissions undergo rigorous peer review of both the abstract and software itself, including documentation, tests, continuous integration, and licensing. The JOSS review process is modeled on the established approach of the rOpenSci collaboration. The entire submission and review process occurs openly on GitHub; articles not yet accepted remain visible and under review until the authors make appropriate changes for acceptance{\textemdash}unlike other journals, articles requiring major revision are not rejected. JOSS published 111 articles in its first year (May 2016{\textendash}2016), with {\textgreater}50 articles under review.},
	language = {en},
	urldate = {2020-11-12},
	booktitle = {Proceedings of {SciPy}},
	publisher = {SciPy},
	author = {Smith, Arfon and Barba, Lorena A. and Githinji, George and Gymrek, Melissa and Huff, Kathryn and Katz, Daniel S. and Madan, Christopher and Mayes, Abigail Cabunoc and Moerman, Kevin M. and Niemeyer, Kyle and Prins, Pjotr and Ram, Karthik and Rokem, Ariel and Teal, Tracy and Valls Guimera, Roman and Vanderplas, Jacob T.},
	month = jul,
	year = {2017},
	note = {10.6084/m9.figshare.5208151.v1},
	file = {Full Text PDF:/Users/huff/Zotero/storage/D5F45YBX/Smith et al. - 2017 - Introducing JOSS The Journal of Open Source Softw.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/99CUXMRM/5208151.html:text/html},
}

@inproceedings{dotson_echo_2020,
	address = {Virtual Meeting},
	series = {Operations and {Power} {Division} {Hybrid} and {Integrated} {Energy} {Systems}},
	title = {Echo {State} {Networks} for {Renewable} {Energy} {Forecasting}},
	shorttitle = {Paper 33110},
	url = {https://www.ans.org/meetings/wm2020/session/view-235/},
	abstract = {Many nuclear power plants are at risk of shutting down due to a combination of policy decisions and financial strain [1]. Accurately predicting the generation from solar and wind may help minimize profit losses for nuclear power plants. Nu- clear power competes with natural gas to fulfill the net demand after accounting for renewable energy sources. Load following gives natural gas an economic edge over nuclear power be- cause natural gas plants can follow grid demand and even shut off when renewable penetration makes the price of electricity go negative [2]. It is possible for existing nuclear plants to load follow somewhat and some French nuclear plants have been retrofitted to follow daily variations in electricity demand [3]. As penetration of solar and wind energy increases around the world, load following will depend less on electric demand pro- files and more on renewable energy profiles. This shift makes load following with current nuclear power plants intractable [4]. Renewable energy challenges the base load electricity production that nuclear provides in the United States by in- troducing grid demand variability. Advanced reactor designs, like some Molten Salt Reactors (MSRs), promise strong load following capabilities due to active 135Xe removal [5]. Unfor- tunately, the most mature MSR designs are at least a decade away from obtaining a commercial license in the United States. The climate crisis is too urgent to wait this long for nuclear power to become fully competitive with natural gas [6].
Variability has been the primary drawback for renewable energy sources like wind turbines, solar PV, and solar concen- trators, since their inception. This flaw worsens as renewable energy penetration increases [4]. Forecasting electricity pro- duction from renewable sources is therefore important for successful management of power systems [7]. Recent studies applied artificial neural networks (ANNs), specifically multi- layer perceptrons, to the task of net load forecasting [7, 8, 9]. These studies made short term forecasts of 4-6 hours but nu- clear plants need accurate forecasts further ahead to facilitate load following. This study will be the first to apply Echo State Networks (ESNs) to the task of net load prediction.},
	urldate = {2020-11-17},
	booktitle = {Proceedings of the 2020 {ANS} {Virtual} {Winter} {Meeting}},
	publisher = {American Nuclear Society},
	author = {Dotson, Samuel G. and Huff, Kathryn D.},
	month = nov,
	year = {2020},
	file = {Dotson and Huff - 2020 - Echo State Networks for Renewable Energy Forecasti.pdf:/Users/huff/Zotero/storage/KWZQ8ZFH/Dotson and Huff - 2020 - Echo State Networks for Renewable Energy Forecasti.pdf:application/pdf;Hybrid and Integrated Energy Systems -- ANS / Meetings / 2020 ANS Virtual Winter Meeting / Technical Sessions:/Users/huff/Zotero/storage/4LY8R26A/view-235.html:text/html},
}

@article{delbert_tiny_2021,
	title = {Tiny {Nuclear} {Reactors} {Can} {Save} {American} {Energy}},
	volume = {2021},
	url = {https://www.popularmechanics.com/science/energy/a34976294/tiny-nuclear-reactors/},
	abstract = {They pack 10 percent of the power of a full-size nuclear plant in just 1 percent of the space.},
	language = {en-US},
	number = {January/February},
	urldate = {2021-01-04},
	journal = {Popular Mechanics},
	author = {Delbert, Caroline},
	collaborator = {Huff, Kathryn},
	month = jan,
	year = {2021},
	note = {Section: Energy},
	file = {Delbert - 2021 - Tiny Nuclear Reactors Can Save American Energy.pdf:/Users/huff/Zotero/storage/7DACQ5AZ/Delbert - 2021 - Tiny Nuclear Reactors Can Save American Energy.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/7B699TPB/tiny-nuclear-reactors.html:text/html},
}

@article{ashraf_preliminary_2021,
	title = {Preliminary design of control rods in the single-fluid double-zone thorium molten salt reactor ({SD}-{TMSR})},
	volume = {152},
	issn = {0306-4549},
	url = {http://www.sciencedirect.com/science/article/pii/S0306454920307313},
	doi = {10.1016/j.anucene.2020.108035},
	abstract = {Recent studies on Molten Salt Reactors (MSRs) showed that the excess reactivity at the beginning of the operation is large for many fueling strategies and must be compensated by a reactivity control system. The current work introduces a reliable safety system based on control rods in addition to the online feed system reactivity control in the Single-fluid Double-zone Thorium-based Molten Salt Reactor (SD-TMSR). Three different initial fissile loadings are considered: 233U, reactor-grade Pu, and transuranic (TRU) elements as a startup fuel. We applied six different absorbing materials to investigate the main operational and safety parameters in the SD-TMSR: natural B4C, enriched B4C with 90\% 10B, HfB2, HfH1.62, Eu2O3, and Gd2O3. The present work focuses on control rod design, integral and differential control rod worth, shutdown margin, and shadowing effects at steady-state. We employed the SERPENT-2 Monte-Carlo code to calculate the reactivity worth and analyze the performance of the reactivity control system. We showed that 233U and reactor-grade Pu startup cores maintain adequate shutdown margin with all considered absorbers. Finally, this paper proposes a design of control rod clusters that compensate the excess reactivity of the SD-TMSR loaded with different initial fissile material.},
	language = {en},
	urldate = {2021-01-05},
	journal = {Annals of Nuclear Energy},
	author = {Ashraf, O. and Rykhlevskii, Andrei and Tikhomirov, G. V. and Huff, Kathryn D.},
	month = mar,
	year = {2021},
	keywords = {Reactivity, Safety, Monte Carlo, Burnup, Online reprocessing, Control rod, MSR, Thorium fuel cycle, Breeding reactor, Monte carlo code},
	pages = {108035},
	file = {Ashraf et al. - 2020 - Preliminary design of control rods in the single-f.pdf:/Users/huff/Zotero/storage/RBGV8RDL/Ashraf et al. - 2020 - Preliminary design of control rods in the single-f.pdf:application/pdf;ScienceDirect Full Text PDF:/Users/huff/Zotero/storage/JCK8UP39/Ashraf et al. - 2021 - Preliminary design of control rods in the single-f.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/8BYZ9JAQ/S0306454920307313.html:text/html},
}

@mastersthesis{fairhurst-agosta_multi-physics_2020,
	address = {Urbana, IL},
	title = {Multi-{Physics} and {Technical} {Analysis} of {High}-{Temperature} {Gas}-{Cooled} {Reactors} for {Hydrogen} {Production}},
	copyright = {Copyright 2020 Roberto Fairhurst Agosta},
	abstract = {The future energy needs require the development of clean energy sources to ease the increasing environmental concerns. High-Temperature Gas-cooled Reactors have several desirable features that make them ideal candidates for the near-future large-scale deployment. Some of these features are a high temperature and high thermal cycle efficiency, which enable a wide range of process heat applications, such as hydrogen production. Implementing hydrogen economies can decarbonize the transport and power sectors, offering an alternative to ease climate change.
This work uses Moltres as the primary simulation tool. Although Moltres original development targeted Molten Salt Reactors, this work studies Moltres applicability to multi-physics simulations of prismatic High-Temperature Gas-cooled Reactors. Multi-physics simulations are necessary for assessing reactor safety characteristics. Ensuring
Moltres{\textquoteright} multi-physics modeling capabilities requires assessing the independent modeling capabilities of the different physical phenomena. Therefore, this thesis breaks down the analysis into three parts: stand-alone neutronics, stand-alone thermal-fluids, and coupled neutronics/thermal-fluids.
Regarding stand-alone neutronics, several analyses compare the results calculated by Moltres and Serpent on an MHTGR-350 model. The first analysis studies the energy group structure effects on the simulation of a fuel column. The results of the study suggest using a 15-energy group structure for attaining a desirable accuracy. The following analysis focuses on the full-core problem and compares different aspects of the simulations, concluding that Moltres obtains reasonably accurate results. The final study on stand-alone neutronics describes Moltres results of Phase I Exercise 1 of the OECD/NEA MHTGR-350 Benchmark. The benchmark exercise proved to be a modeling challenge, requiring the implementation of several approximations. For the most part, this thesis demonstrates Moltres{\textquoteright} capability to simulate stand-alone neutronics of prismatic High-Temperature Gas-cooled Reactors.
Regarding stand-alone thermal-fluids, several studies compare Moltres results to previously published results.
These studies focus on local models such as the unit cell and the fuel column problems, for which Moltres temperature results differ by less than 2\% from the published results. Further studies analyze the possibility of extending the thermal-fluids model implemented in the previous problems to a full-core simulation, finding a high memory
requirement imposed by the simulations. The full-core simulations focus on Phase I Exercise 2 of the benchmark, for which the implementation of a two-level approach in Moltres was necessary. The study{\textquoteright}s temperatures were within an 11.3\% difference to the published results, concluding that further analysis is required.
Regarding coupled neutronics/thermal-fluids, the analysis describes Phase I Exercise 3 of the benchmark. The exercise uses a simplified model that helps visualize some of the essential aspects of multi-physics simulations in Moltres. This exercise finds some areas of improvement in Moltres{\textquoteright} model and sets a basis for future work.
This thesis aligns with the University of Illinois{\textquoteright} goals to reduce carbon emissions from its campus{\textquoteright}s electricity generation and transportation sectors. This work focuses on two main analysis by introducing a nuclear reactor coupled to a hydrogen plant as a solution. The first analysis evaluates the conversion of the university fleet and the mass transit transport system in Urbana-Champaign to Fuel Cell Electric Vehicles. The second analysis investigates the duck curve phenomenon in the university{\textquoteright}s grid and introduces a mitigation strategy that may reduce the reliance on dispatchable sources. These studies emphasize how nuclear energy and hydrogen production can potentially mitigate climate change.},
	language = {English (US)},
	school = {University of Illinois at Urbana-Champaign},
	author = {Fairhurst-Agosta, Roberto},
	month = dec,
	year = {2020},
	file = {Fairhurst-Agosta - Multi-Physics and Technical Analysis of High-Tempe.pdf:/Users/huff/Zotero/storage/PTK9576U/Fairhurst-Agosta - Multi-Physics and Technical Analysis of High-Tempe.pdf:application/pdf},
}

@misc{huff_nuclear_2021,
	address = {Virtual},
	type = {Panel},
	title = {The {Nuclear} {Nonproliferation} {Treaty} at 50 years},
	url = {https://www.ans.org/webinars/view-npt2021/},
	abstract = {An expert panel will take a look back at the origins of the Nuclear Non-Proliferation Treaty (NPT) as well as discuss its future. Attendees will take a walk through the NPT{\textquoteright}s progression as well as examine the status of non-proliferation, disarmament, and the nuclear energy cooperation. Other topics to be covered include:

- Nuclear weapons today and the status of other arms control agreements
- What can we do as professionals and citizens
- The future of the NPT

Panelists:

Angela Di Fulvio, Assistant Professor of Nuclear, Plasma \& Radiological Engineering, University of Illinois Urbana-Champaign
Kathryn Huff, Assistant Professor of Nuclear, Plasma \& Radiological Engineering, University of Illinois Urbana-Champaign
Richard Meserve, President Emeritus, Carnegie Institution for Science
Zia Mian, Co-Director, Program on Science and Global Security, Princeton University
Stewart Prager, Professor of Astrophysical Sciences and Affiliated Faculty, Program on Science and Global Security, Princeton University

Moderator:

Craig Piercy, ANS Executive Director/CEO},
	author = {Huff, Kathryn},
	month = feb,
	year = {2021},
}

@misc{huff_essential_2021,
	address = {University of California, Berkeley},
	type = {Colloquium},
	title = {The {Essential} {Role} of {Universities} in {Advanced} {Reactor} {Deployment}},
	url = {https://nuc.berkeley.edu/the-essential-role-of-universities-in-advanced-reactor-deployment/},
	abstract = {Many University TRTRs were shut down in the 1980s \& 1990s as student enrollments waned. In the 2000s, student enrollment in nuclear engineering and enthusiasm for carbon-free nuclear energy has rebounded mightily, but no new university TRTRs have been built in nearly 30 years. Simultaneous with this widening gap in hands-on training, unprecedented federal funding to demonstrate and commercialize advanced reactors has been distributed to companies promising a bright future for advanced nuclear energy. But, in this future, who will objectively test these reactors, train their operators, educate their reactor engineers, and improve the technology through innovative experiments?

In this talk, I'll suggest that universities remain poised to play many of these roles in the future of next-generation nuclear reactor deployment and university campuses are uniquely suited for early deployments. We at UIUC envision a next-generation university test, research, and training reactor that could underpin advanced reactor commercialization toward national leadership in a clean, sustainable energy future. Our vision for the deployment of a next-generation university TRTR aims to amplify the profound expertise at campuses in research, education, and power production to address the urgent need for advanced reactor prototype testing as well as next-generation research toward integration with carbon-free energy technologies. I will describe a vision of the future in which universities and their research can and must play a significant role in prototype testing next-generation reactors, support commercial licensing and deployment, conduct operations research, drive innovations in associated technologies, and train a next-generation workforce to operate and maintain these next-generation devices.},
	author = {Huff, Kathryn D.},
	month = jan,
	year = {2021},
}

@misc{daniel_s_katz_josss_2021,
	type = {Blog for the {Journal} of {Open} {Source} {Software} {\textbullet} https://joss.theoj.org},
	title = {{JOSS}'s {Commitment} to the {Principles} of {Open} {Scholarly} {Infrastructure} {\textbar} {Journal} of {Open} {Source} {Software} {Blog}},
	url = {https://blog.joss.theoj.org/2021/02/JOSS-POSI},
	abstract = {Blog for the Journal of Open Source Software {\textbullet} {\textless}a href='https://joss.theoj.org'{\textgreater}https://joss.theoj.org{\textless}/a{\textgreater}, Blog for the Journal of Open Source Software {\textbullet} {\textless}a href='https://joss.theoj.org'{\textgreater}https://joss.theoj.org{\textless}/a{\textgreater}},
	urldate = {2021-02-14},
	journal = {Journal of Open Source Software Blog},
	author = {{Daniel S. Katz} and {Arfon Smith} and {Kyle E. Niemeyer} and {Kathryn D. Huff}},
	month = feb,
	year = {2021},
	file = {Snapshot:/Users/huff/Zotero/storage/B5FGZJQC/JOSS-POSI.html:text/html},
}

@inproceedings{park_multiphysics_2021,
	address = {Virtual Meeting},
	series = {Reactor {Analysis} {Methods} - {I}},
	title = {Multiphysics {Benchmark} {Results} from {Moltres}},
	url = {https://www.ans.org/meetings/am2021/session/view-587/},
	booktitle = {Proceedings of the 2021 {ANS} {Virtual} {Annual} {Meeting}},
	publisher = {American Nuclear Society},
	author = {Park, Sun Myung and Huff, Kathryn D},
	month = jun,
	year = {2021},
	note = {(Submitted before May 2021)},
	file = {Park and Huff - 2021 - Multiphysics Benchmark Results from Moltres.pdf:/Users/huff/Zotero/storage/DI37TPGK/Park and Huff - 2021 - Multiphysics Benchmark Results from Moltres.pdf:application/pdf;Reactor Analysis Methods - I -- ANS / Meetings / 2021 ANS Virtual Annual Meeting / Technical Sessions:/Users/huff/Zotero/storage/PSC9JE66/view-587.html:text/html},
}

@article{dalessio_photo_2021,
	address = {Urbana, IL},
	chapter = {Photo 120 of 143: Katy Huff, Assistant Professor, Nuclear, Plasma, and Radiological Engineering},
	edition = {Editor's Pick},
	title = {Photo {Gallery}: 143 masked {Illini} past and present ({Part} 6)},
	shorttitle = {Photo {Gallery}},
	url = {https://www.news-gazette.com/coronavirus/photo-gallery-143-masked-illini-past-and-present-part-6/collection_f3c17cbc-b770-5f16-87de-2c3eea3e4309.html},
	abstract = {As part of our weekly Insider page, Editor Jeff D'Alessio asked 600-plus Illini of today and yesteryear to send us a selfie of their face covering of choice. Here's Part},
	language = {en},
	urldate = {2021-03-11},
	journal = {The News-Gazette},
	author = {D'Alessio, Jeff},
	collaborator = {Huff, Kathryn D.},
	month = mar,
	year = {2021},
	pages = {120},
	file = {Jeff D'Alessio and Kathryn D. huff - 2021 - PHOTO GALLERY 143 masked Illini past and present .pdf:/Users/huff/Zotero/storage/RSKNY737/Jeff D'Alessio and Kathryn D. huff - 2021 - PHOTO GALLERY 143 masked Illini past and present .pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/HIY9H33A/collection_f3c17cbc-b770-5f16-87de-2c3eea3e4309.html:text/html},
}

@misc{huff_role_2020,
	address = {West Lafayette, IN (virtual)},
	type = {Conference},
	title = {The {Role} of {Universities} in {Advanced} {Reactor} {Deployment}},
	url = {https://trtr.org/wp-content/uploads/2020/10/2020-TRTR-Program.pdf},
	abstract = {Many University TRTRs were shut down in the 1980s \& 1990s as student enrollments waned. In the 2000s, student enrollment in nuclear engineering and enthusiasm for carbon-free nuclear energy has rebounded mightily, but no new university TRTRs have been built in nearly 30 years. Simultaneous with this widening gap in hands-on training, unprecedented federal funding to demonstrate and commercialize advanced reactors has been distributed to companies promising a bright future for advanced nuclear energy. But, in this future, who will objectively test these reactors, train their operators, educate their reactor engineers, and improve the technology through innovative experiments?

In this talk, I'll suggest that universities remain poised to play many of these roles in the future of next-generation nuclear reactor deployment and university campuses are uniquely suited for early deployments. We at UIUC envision a next-generation university test, research, and training reactor that could underpin advanced reactor commercialization toward national leadership in a clean, sustainable energy future. Our vision for the deployment of a next-generation university TRTR aims to amplify the profound expertise at campuses in research, education, and power production to address the urgent need for advanced reactor prototype testing as well as next-generation research toward integration with carbon-free energy technologies. I will describe a vision of the future in which universities and their research can and must play a significant role in prototype testing next-generation reactors, support commercial licensing and deployment, conduct operations research, drive innovations in associated technologies, and train a next-generation workforce to operate and maintain these next-generation devices.},
	author = {Huff, Kathryn D.},
	month = sep,
	year = {2020},
}

@misc{huff_nuclear_2020,
	address = {West Lafayette, IN (virtual)},
	type = {Conference},
	title = {Nuclear {In} {Higher} {Education}},
	url = {https://www.winus.org/wp-content/uploads/2020/08/2020-Region-III-Conference-Flyer.pdf},
	author = {Huff, Kathryn D.},
	month = sep,
	year = {2020},
}

@misc{huff_atomic_2020,
	address = {Staerkel Planetarium},
	type = {Public {Science} {Lecture} ({Virtual})},
	title = {Atomic {Advancements}},
	url = {https://www.parkland.edu/Audience/Community-Business/Parkland-Presents/Planetarium/Events/Calendar?trumbaEmbed=view%3Devent%26eventid%3D460921415},
	abstract = {During this virtual event, Katy Huff (UIUC, Nuclear, Plasma, and Radiological Engineering) will present what's new in nuclear energy. This talk will demystify transformative new reactor, fuel, and recycling technologies ready to support a clean energy future worldwide.},
	author = {Huff, Kathryn D.},
	month = nov,
	year = {2020},
}

@misc{huff_role_2020-1,
	address = {Washington, DC (virtual)},
	type = {Invited {Presentation}},
	title = {The {Role} of {Universities} in {Advanced} {Reactor} {Deployment}},
	url = {https://www.youtube.com/watch?v=6DCVnKd5qdA},
	author = {Huff, Kathryn D.},
	month = oct,
	year = {2020},
}

@misc{huff_general_2020,
	address = {Virtual Meeting},
	type = {Video {Snippet} on {Transformation} of {University} {Research} {Reactors}},
	title = {General {Chair}'s {Special} {Session} {Nuclear} {Science} and {Industry}: {The} next transformation},
	url = {https://www.ans.org/meetings/wm2020/session/view-299/},
	urldate = {2021-03-15},
	author = {Huff, Kathryn},
	month = nov,
	year = {2020},
	file = {General Chair's Special Session -- ANS / Meetings / 2020 ANS Virtual Winter Meeting / Technical Sessions:/Users/huff/Zotero/storage/MWGRDR3A/view-299.html:text/html},
}

@misc{adams_atomic_2020,
	address = {https://podcasts.google.com/feed/aHR0cHM6Ly9hdG9taWNpbnNpZ2h0cy5jb20vcG9kY2FzdC9mZWVkLw},
	title = {Atomic {Show} \#285 - {MMR} at {Illinois} - {Atomic} {Insights}},
	shorttitle = {{MMR} {At} {Illinois}},
	url = {https://atomicinsights.com/atomic-show-285-mmr-at-illinois/},
	abstract = {The University of Illinois at Urbana-Champaign has a stretch goal of completing its next research and test reactor by the end of 2025. It has assembled a team},
	language = {en-US},
	journal = {Section: Advanced Atomic Technologies},
	author = {Adams, Rod},
	collaborator = {Brooks, Caleb S. and Huff, Kathryn D.},
	month = nov,
	year = {2020},
	file = {Snapshot:/Users/huff/Zotero/storage/857AU7XY/atomic-show-285-mmr-at-illinois.html:text/html;Snapshot:/Users/huff/Zotero/storage/3C2Q6TJQ/aHR0cHM6Ly9hdG9taWNpbnNpZ2h0cy5jb20vP3A9MjEwODg.html:text/html},
}

@inproceedings{bachmann_enriched_2021,
	address = {Virtual},
	title = {Enriched {Uranium} {Supply} {Requirements} for the {Transition} to {Advanced} {Reactors}},
	abstract = {Current nuclear reactors employed in the United States use Low Enriched Uranium (LEU)fuel enriched to no more than 5\%.  New reactor designs, such as the Ultra Safe Nuclear Cor-poration (USNC) Micro Modular Reactor (MMR)TM, will require High Assay Low EnrichedUranium (HALEU) fuel enriched between 5-20\%.  To meet HALEU fuel requirements, theU.S. Department of Energy is considering recovery and downblending of High Enriched Ura-nium (HEU) fuel and enriching natural uranium to the required levels [1], with each of thesemethods containing their own limitations.  Recovery and downblending of HEU fuel is lim-ited by the existing physical supply of HEU as well as downblending capacity.  Enrichment ofnatural uranium is limited by centrifuge capacity, in terms of Separative Work Unit (SWU).This work aims to quantify the resource requirements of the current U.S. reactor fleetand of the transition to different reactors that require HALEU fuel.  Fuel cycle simulationsare completed usingCyclus, an agent-based fuel cycle simulator [2].  Transition scenariosconsidered include use of the USNC MMRTMand the X-energy Xe-100TMreactor, which bothrequire HALEU fuel.  Resource requirements of interest include enriched fuel requirementsat each enrichment level, HEU required to meet HALEU demand, and natural uranium andSWU required to meet HALEU demand. These metrics will inform the material requirementsand  provide  insight  into  the  best  method  to  meet  fuel  requirements  for  these  transitionscenarios},
	language = {English},
	booktitle = {Proceedings of the {American} {Nuclear} {Society} 2021 {National} {Student} {Conference},},
	author = {Bachmann, Amanda M. and Huff, Kathryn D.},
	month = apr,
	year = {2021},
	file = {Bachmann - 2021 - Enriched Uranium Supply Requirements for the Trans.pdf:/Users/huff/Zotero/storage/5Z2SIKNQ/Bachmann - 2021 - Enriched Uranium Supply Requirements for the Trans.pdf:application/pdf},
}

@mastersthesis{chaube_large-eddy_2021,
	address = {Urbana, IL},
	title = {Large-{Eddy} {Simulations} of {Recirculation} {Zones} in {Channel}-{Type} {Molten} {Salt} {Reactors}},
	copyright = {Copyright 2021 Anshuman Chaube},
	abstract = {In an effort to curb carbon emissions and mitigate the effects of climate change, energy policymakers are considering advanced nuclear reactors as a potential source of clean base-load energy. Once such family of reactor designs is called the Molten Salt Reactor, which has been successfully demonstrated experimentally during the operation of the Molten Salt Reactor Experiment(MSRE) at the Oak-Ridge National Laboratory during the 1960s. Thermal-hydraulic simulations of this reactor are an important step towards validating and verifying simulation tools for other molten salt reactor designs and exploring the potential of such reactors for licensing. Modern CFD simulations of the MSRE reactor core often discount the effects of turbulence in this reactor due to the low Reynolds number inside the MSRE channels. They also neglect the pyramidal tip at the top of the moderator graphite blocks called stringers. However, recent research indicates turbulence can play a significant role in compact reactor cores at relatively low Reynolds numbers. Our main concern is entrainment of fuel salt in recirculation zones and subsequent creation of localised hotspots. Therefore, we investigated the presence of such recirculation zones and the effect of the tip-shape on turbulence and stationary vortices in the upper plenum.
We analysed the flow around an MSRE graphite stringer using large eddy simulations performed in Nek5000. We also studied the effects of varying the size and shape of the stringer-tip using Nek5000{\textquoteright}s mesh deformation capabilities. To our knowledge, this work is the first effort to apply large eddy simulations to the MSRE and study the effects of geometry-induced turbulence and recirculation within the MSRE. We analysed the output data and found that salt recirculation vortices do exist and geometry and turbulence affect the salt flow in the upper plenum. But fuel salt recirculation does not impact the temperature of the salt or graphite significantly. We also determined the ideal tip-shape that minimises salt recirculation and entrapment. We found that a pyramidal tip with an apex half-angle of 45{\textopenbullet} disrupts recirculation, encourages mixing, and improves heat transfer, keeping salt and graphite temperatures low, whereas angles that are as small as 30{\textopenbullet} or large enough to tend towards a flat-top lead to hotter temperatures. Implications for the design and simulation of similar channel-type molten salt reactors are discussed.},
	language = {English},
	school = {University of Illinois at Urbana-Champaign},
	author = {Chaube, Anshuman},
	collaborator = {Huff, Kathryn D. and Fischer, Paul},
	month = apr,
	year = {2021},
	file = {Chaube - 2021 - Large-Eddy Simulations of Recirculation Zones in C.pdf:/Users/huff/Zotero/storage/XLFNYFQK/Chaube - 2021 - Large-Eddy Simulations of Recirculation Zones in C.pdf:application/pdf},
}

@techreport{dotson_economic_2021,
	address = {Urbana, IL},
	type = {Technical {Report}},
	title = {Economic and {Carbon} {Impacts} of {Potential} {Illinois} {Nuclear} {Plant} {Closures}: {The} {Cost} of {Closures}},
	shorttitle = {Comissioned by {Nuclear} {Matters}},
	url = {github.com/arfc/2021-04-nm-illinois},
	abstract = {n August 27, 2020, Exelon Generation announced planned premature clo- sures of two Illinois nuclear plants (4 reactor units) which compete eco- nomically with fossil fueled plants within the Pennsylvania-New Jersey- Maryland (PJM) interconnection [1]. This report quantitatively explores how these closures would undermine economic and decarbonization goals in the state of Illinois, such as an aggressive target to achieve a zero carbon electric grid by 2030.
Previous energy systems research has shown that such clean energy goals cannot be reached if nuclear plants prematurely retire [2, 3, 4]. In particular, the February 2021 National Academy of Sciences, Engineering, and Medicine consensus report, {\textquotedblleft}Accelerating Decarbonization of the U.S. Energy System,{\textquotedblright} determined unequivocally that US decarbonization will require keeping existing nuclear plants open [2]. Consistent with that liter- ature, our simulations indicate that decarbonization in Illinois will require not only maintenance but expansion of nuclear energy capacity.},
	language = {english},
	number = {UIUC-ARFC-2021-02},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Dotson, Samuel G. and Bachmann, Amanda M. and Richter, Zo{\"e} M. and Panczyk, Nataly R. and Ryan, Nathan S. and Balla, Anna C. and Fanning, Erin R.},
	editor = {Huff, Kathryn D. and Munk, Madicken},
	month = may,
	year = {2021},
	keywords = {cyclus, arfc, report, nuclear fuel cycle},
	pages = {1--20},
}

@techreport{turkmen_milestone_2021,
	address = {Urbana, IL},
	type = {Milestone {Report}},
	title = {Milestone 2.3 {Report}: {SaltProc} {Sensitivity} {Analysis}, {Fuel} processing system design},
	shorttitle = {Contract {DE}-{AR0000983}, {Enabling} {Load} {Following} {Capability} in the {Transatomic} {MSR}},
	abstract = {The University of Illinois, Urbana-Champaign (UIUC) is engaged in work to develop a fuel processing system that enables load-following in Molten Salt Reactors (MSRs), an important ability that allows nuclear power plants to ramp electricity production up or down to meet changing electricity demand. Nuclear reactions in MSRs produce unwanted byproducts (such as xenon and krypton) that can adversely affect power production. In steady, baseload operation, these byproducts form and decay at the same rate. When electricity production is ramped down, however, the byproducts start to be produced at a greater rate than they decay, leading to a buildup within the reactor. When power production must be once again increased, the response rate is slowed by the time needed for the byproducts to reach their equilibrium level (determined by the radioactive decay half-life, which is on the order of hours). Thus, buildup of these unwanted byproducts resulting from ramping down inhibit proper load following for molten salt reactors. Fortunately, MSRs transport fuel in a flowing molten salt fuel loop, which means that a section of the reactor, outside the core, can be leveraged for fuel processing and "cleanup." The team will determine the feasibility of removal of these unwanted byproducts and de- sign a fuel reprocessing system, removing a major barrier to commercialization for molten salt reactors.

Toward this work, we initiated the Fuel Cycle Simulation task (Task 2) in August 2018 to more realistically model the online reprocessing system of the Transatomic Power (TAP) MSR. A Python toolkit, SaltProc v0.1 [1{\textendash}3], was developed to represent the simplified online fuel salt processing of a Molten Salt Breeder Reactor (MSBR). More recently, an advanced SaltProc version (SaltProc v0.2) was developed to generically simulate complex molten salt fuel reprocessing systems, including the TAP system, incorporating user-parametrized components into the fuel salt processing design. This report summarizes the progress we have made towards milestone M2.1: Demonstrate SaltProc and the steps toward the subsequent Task 2 objectives.},
	language = {english},
	number = {UIUC-ARFC-2021-01},
	institution = {University of Illinois at Urbana-Champaign},
	author = {Turkmen, Mehmet and Chen, Jiaqi},
	editor = {Huff, Kathryn and Brooks, Caleb S. and Kozlowski, Tomasz and Stubbins, James F. and Heuser, Brent},
	collaborator = {Lee, Alvin and Zhen, Li and Rykhlevskii, Andrei},
	month = mar,
	year = {2021},
	keywords = {cyclus, nuclear engineering, arfc, report, molten salt reactor, nuclear fuel cycle},
	pages = {1--26},
}

@inproceedings{bachmann_modeling_2021,
	address = {Virtual},
	title = {Modeling {Material} {Requirements} of the {Transition} to {HALEU} {Fueled} {Reactors}},
	abstract = {For many fuel cycle simulators, it is currently up to the user to define a deployment scheme of supporting facilities or provide an infinite inventory of commodities to ensure that there is no gap in the supply chain. To ease setting up nuclear fuel cycle simulations, Nuclear Fuel Cycle (NFC) simulators should bring demand responsive deployment decisions into the dynamics of the simulation logic. In this work, we develop demand driven deployment capabilities in Cyclus, d3ploy. User-controlled capabilities such as supply/ capacity buffers, constraint deployment, prediction algorithms, and installed capacity deployment were introduced in d3ploy to give a user the tools to minimize commodity undersupply in a simulation. We demonstrate d3ploy{\textquoteright}s capability to automatically deploy fuel cycle facilities to meet various types of user-defined power demands: constant, linearly increasing, and sinusoidal.},
	booktitle = {Proceedings of the {Technical} {Workshop} on {Fuel} {Cycle} {Simulation} 2021},
	author = {Bachmann, Amanda M.},
	collaborator = {Huff, Kathryn D},
	month = jun,
	year = {2021},
	file = {2021-bachmann-twofcs.pdf:/Users/huff/Zotero/storage/UIHQHTI9/2021-bachmann-twofcs.pdf:application/pdf;Bachmann_twofcs_2021.pdf:/Users/huff/Zotero/storage/ZLMVKZTM/Bachmann_twofcs_2021.pdf:application/pdf},
}

@inproceedings{bachmann_comparing_2021,
	address = {Virtual Meeting},
	title = {Comparing {HALEU} {Demand} {Aong} {Advanced} {Reactor} {Fuel} {Cycle} {Transitions}},
	volume = {124},
	url = {https://www.ans.org/pubs/transactions/article-49551/},
	urldate = {2021-06-29},
	booktitle = {Proceedings of the 2021 {ANS} {Virtual} {Annual} {Meeting}},
	author = {Bachmann, Amanda M. and Huff, Kathryn D.},
	month = jun,
	year = {2021},
	note = {(Submitted before May 2021)},
	pages = {134--137},
	file = {Bachmann and Huff - 2021 - Comparing HALEU Demand Aong Advanced Reactor Fuel .pdf:/Users/huff/Zotero/storage/ZS9KY5RW/Bachmann and Huff - 2021 - Comparing HALEU Demand Aong Advanced Reactor Fuel .pdf:application/pdf;Transactions -- ANS / Publications / Transactions:/Users/huff/Zotero/storage/TT3RKVFW/article-49551.html:text/html},
}

@misc{park_results_2021,
	title = {Results from {Moltres} for the {CNRS} {Benchmark}},
	url = {https://zenodo.org/record/5534964},
	doi = {10.5281/zenodo.5534964},
	abstract = {Raw data from running the CNRS benchmark with Moltres.},
	language = {eng},
	urldate = {2021-09-28},
	publisher = {Zenodo},
	author = {Park, Sun Myung and Munk, Madicken and Huff, Kathryn D.},
	month = sep,
	year = {2021},
	file = {Zenodo Snapshot:/Users/huff/Zotero/storage/ME29K27S/5534964.html:text/html},
}

@article{chaube_role_2021,
	title = {The role of current and emerging technologies in meeting {Japan}{\textquoteright}s mid- to long-term carbon reduction goals},
	volume = {304},
	issn = {0306-2619},
	url = {https://www.sciencedirect.com/science/article/pii/S0306261921010308},
	doi = {10.1016/j.apenergy.2021.117669},
	abstract = {Using Japan as a proxy for a developed nation, we investigated the role of existing and nascent technologies in curbing carbon emissions. We simulated possible pathways to meeting 2030 and 2050 emission targets within the Japanese electricity supply sector using a single-region model in The Integrated MARKAL-EFOM System (TIMES). Critically, our simulations incorporate novel technologies like hydrogen electrolysers, carbon capture, photochemical water splitting, and emerging photovoltaic cells, assess long-term impacts up to the year 2100, and include life-cycle emissions and learning curves for parameters such as investment cost, efficiency, and emission coefficients. Results indicate that a hybrid approach, using nuclear power and hydrogen from renewable energy-based electrolysis, is cost-effective and provides long-term emission reduction along with energy security. Nuclear, wind, solar, and hydrogen from renewables emerge as key emission reduction technologies, while natural gas with carbon capture plays a minor role in achieving emission reduction targets.},
	language = {en},
	urldate = {2021-09-02},
	journal = {Applied Energy},
	author = {Chaube, Anshuman and Chapman, Andrew and Minami, Akari and Stubbins, James and Huff, Kathryn D.},
	month = dec,
	year = {2021},
	keywords = {Nuclear power, Japan, Energy model, Carbon capture, Hydrogen fuel cell},
	pages = {117669},
	file = {Chaube et al. - 2021 - The role of current and emerging technologies in m.pdf:/Users/huff/Zotero/storage/F9D3PCYP/Chaube et al. - 2021 - The role of current and emerging technologies in m.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/XWBGANTC/S0306261921010308.html:text/html},
}

@inproceedings{petrovic_preliminary_2021,
	address = {Virtual},
	title = {Preliminary {Results} of the {NEA} {FHR} {Benchmark} {Phase} {I}-{A} and {I}-{B} ({Fuel} {Element} 2-{D} {Benchmark})},
	url = {https://www.ans.org/pubs/proceedings/article-50163/},
	abstract = {Under the auspices on OECD-NEA, a benchmark has been initiated to assess state of the art modelling and simulation capabilities for Fluoride salt-cooled High-temperature Reactors (FHRs) with TRISO fuel embedded in fuel plates ({\textquotedblleft}planks{\textquotedblright}) of hexagonal fuel elements. Benchmark phases I-A and I-B involve reactor physics analysis of a representative fuel element, without and with depletion. Several configurations are considered (e.g., unrodded and rodded configuration, presence of burnable absorbers, variable enrichment). Parameters compared include multiplication factor, reactivity coefficients, flux distribution, neutron spectrum and isotopic composition change with burnup. Seven organizations from four countries are taking part in this blind-benchmark exercise, using Monte Carlo and deterministic methods. Given the complex combination of materials and geometry, the FHR benchmark is expected to be challenging, particularly for deterministic codes. As the nuclear data libraries underpinning both deterministic and Monte Carlo methods have had limited testing for FHR systems, and molten salt systems in general, the benchmark aims to provide feedback to both the nuclear data community as well as molten salt reactor designers with regards to the variance of results with different nuclear data sources. This paper reports on the current results submitted and provides comparisons and analysis. Overall, the observed agreement is satisfactory, although notable differences are identified in specific cases, suggesting need for further in-depth analysis of those cases.},
	urldate = {2021-10-18},
	booktitle = {Proceedings of {ANS} {M}\&{C} 2021},
	publisher = {American Nuclear Society},
	author = {Petrovic, Bojan and Ramey, Kyle and Hill, Ian and Losa, E. and Elsawi, M. and Wu, Z. and Lu, C. and Gonzalez, J. and Novog, D. and Chee, Gwendolyn and Huff, Kathryn D. and Margulis, M. and Read, N. and Shwegaraus, Eugene},
	month = oct,
	year = {2021},
	note = {(Submitted before May 2021)},
	pages = {1924--1933},
	file = {Petrovic et al. - 2021 - Preliminary Results of the NEA FHR Benchmark Phase.pdf:/Users/huff/Zotero/storage/PPH8PL2E/Petrovic et al. - 2021 - Preliminary Results of the NEA FHR Benchmark Phase.pdf:application/pdf;Proceedings -- ANS / Publications / Proceedings:/Users/huff/Zotero/storage/BEFPZY9F/article-50163.html:text/html},
}

@article{chapman_cultural_2021,
	title = {The cultural dynamics of energy: {The} impact of lived experience, preference and demographics on future energy policy in the {United} {States}},
	volume = {80},
	issn = {2214-6296},
	shorttitle = {The cultural dynamics of energy},
	url = {https://www.sciencedirect.com/science/article/pii/S2214629621003248},
	doi = {10.1016/j.erss.2021.102231},
	abstract = {Cultural diversity is increasing in the US, which is likely to have an impact on preferences toward future energy policy. This research investigates people{\textquoteright}s lived experience and preferences through a nationally representative survey (n~=~3000) regarding the energy system, and how these relate to cultural group and other demographics. Our study highlights the influence of cultural background in the US, alongside educational achievement and income level on perceptions toward the energy system and energy policy. Through rigorous multivariate statistical evaluation of cultural groupings, income and education on energy system preferences and lived experience, we identified cultural groups that experience energy affordability differently, irrespective of income or educational achievement. For energy policy issue and factor importance, we identify a positive link with educational achievement and income, varying across cultural grouping. Overall, Native Hawaiian or other Pacific Islanders and American Indian and Native Alaskans had a muted response to energy policy issues and energy system factors compared to their peers. Our findings identified a need to enhance overall educational outcomes to engender more positive attitudes toward improving the environment, and the need for policy makers to be aware of cultural group preferences to enable development of energy policies which improve recognition justice outcomes.},
	language = {en},
	urldate = {2021-10-18},
	journal = {Energy Research \& Social Science},
	author = {Chapman, Andrew and Shigetomi, Yosuke and Chandra Karmaker, Shamal and Baran Saha, Bidyut and Huff, Kathryn and Brooks, Caleb and Stubbins, James},
	month = oct,
	year = {2021},
	keywords = {Energy policy, Culture, Demographics, Energy affordability, Energy justice, Recognition},
	pages = {102231},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/4V9TPZ2F/S2214629621003248.html:text/html},
}

@misc{huff_panel_2021,
	address = {U.S. Department of Energy Hydrogen Program},
	type = {Panel},
	title = {Panel {Discussion}: {H2}@{Scale} {Opportunities} {And} {Activities} at {DOE}},
	shorttitle = {https://www.youtube.com/watch?v={JDpJchIqrlg}\&feature=emb\_imp\_woyt},
	url = {https://www.annualmeritreview.energy.gov/},
	urldate = {2021-10-20},
	author = {Huff, Kathryn D. and Speakes-Backman, Kelly and Wilcox, Jennifer and Binkley, Stephen},
	month = jun,
	year = {2021},
	note = {https://www.annualmeritreview.energy.gov/assets/pdfs/2021-amr-plenary-schedule.pdf},
	file = {Hydrogen Program Annual Merit Review and Peer Evaluation Meeting:/Users/huff/Zotero/storage/8VHWFAMZ/www.annualmeritreview.energy.gov.html:text/html},
}

@misc{huff_selectusa_2021,
	address = {virtual},
	type = {Panel},
	title = {{SelectUSA} {Investment} {Summit} {Civil} {Nuclear} {Energy} {Roundtable}},
	url = {https://www.selectusa.gov/events/past-landing},
	author = {Huff, Kathryn},
	month = jun,
	year = {2021},
}

@misc{huff_future_2021,
	address = {Argonne National Laboratory},
	type = {Instagram {Live}},
	title = {The {Future} of {Nuclear} {Energy} and {Its} {Role} in a {Clean} {Energy} {Economy} {\textbar} {Argonne} {National} {Laboratory}},
	url = {https://www.anl.gov/event/the-future-of-nuclear-energy-and-its-role-in-a-clean-energy-economy},
	abstract = {How will innovations in nuclear technology influence our transition to a fully clean energy economy? 

Join the Department of Energy{\textquoteright}s Kathryn Huff, the Acting Assistant Secretary and Principal Deputy Assistant Secretary for the Office of Nuclear Energy, and Argonne{\textquoteright}s Andrew Breshears as they discuss the future of nuclear energy.},
	language = {en},
	urldate = {2021-10-20},
	author = {Huff, Kathryn D. and Breshears, Andrew},
	month = jun,
	year = {2021},
	note = {https://www.instagram.com/tv/CQtcABTDlLo/},
	file = {Snapshot:/Users/huff/Zotero/storage/ZBLNMFYZ/the-future-of-nuclear-energy-and-its-role-in-a-clean-energy-economy.html:text/html},
}

@misc{argonne_internal_channel_argonne_2021,
	type = {Congratulatory video},
	title = {Argonne 75th {Anniversary} {Congratulatory} {Message} from {Kathryn} {Huff}, {Principal} {Deputy} {Assistant} {Secretary} for {Nuclear} {Energy}, {U}.{S}. {Department} of {Energy}},
	url = {https://www.youtube.com/watch?v=9xQxoUTA_2w},
	urldate = {2021-10-20},
	author = {{Argonne Internal Channel}},
	month = jun,
	year = {2021},
	note = {https://www.anl.gov/75th-anniversary/Congratulatory-Messages},
}

@misc{huff_american_2021,
	address = {Third Way (virtual)},
	type = {Keynote},
	title = {The {American} {Jobs} {Plan}: {Opportunities} for {Advanced} {Nuclear} and {Union} {Workers} {\textendash} {Third} {Way}},
	shorttitle = {https://www.youtube.com/watch?v={1Oy5s7aXTlM}},
	url = {https://www.thirdway.org/events/the-american-jobs-plan-opportunities-for-advanced-nuclear-and-union-workers},
	abstract = {The first advanced nuclear power plants are just years away from construction. With the right federal support, the United States can turn demonstration projects into a full-scale industry and tens of thousands of high-wage, high-skill, union jobs.

Please join Third Way for a virtual event on Tuesday, June 22, at 3:00 PM ET to discuss how policies like the American Jobs Plan can get one of the nation{\textquoteright}s newest clean energy industries up and running. We{\textquoteright}ll explore how to develop the domestic supply chain while building on the nuclear sector{\textquoteright}s strong record of supporting union workers in construction, manufacturing, and engineering. We{\textquoteright}ll hear from industry experts, union leaders, and the Biden Administration on ways to advance America{\textquoteright}s economic and workforce goals while delivering new tools to fight climate change},
	urldate = {2021-10-20},
	author = {Huff, Kathryn D.},
	month = jun,
	year = {2021},
	note = {https://www.youtube.com/watch?v=eEl8cWM7sEw\&feature=emb\_imp\_woyt},
	file = {Snapshot:/Users/huff/Zotero/storage/QJA23MGN/the-american-jobs-plan-opportunities-for-advanced-nuclear-and-union-workers.html:text/html},
}

@misc{huff_testimony_2021,
	address = {Washington D.C.},
	title = {Testimony of {Dr}. {Kathryn} {Huff} {Acting} {Assistant} {Secretary} {Office} of {Nuclear} {Energy} {U}.{S}. {Department} of {Energy} on {Judicious} {Spending} to {Enable} {Success} at the {Office} of {Nuclear} {Energy}. {U}.{S}. {House} {Committee} on {Science}, {Space}, and {Technology} {Subcommittee} on {Energy} and {Subcommittee} on {Investigations} and {Oversight}. 117th {Congress}, {Session} 1.},
	shorttitle = {Joint {Investigations} \& {Oversight} and {Energy} {Subcommittees} {Hearing} - {Judicious} {Spending} to {Enable} {Success} at the {Office} of {Nuclear} {Energy}},
	url = {https://science.house.gov/2021/10/joint-investigations-oversight-and-energy-subcommittees-hearing-judicious},
	publisher = {U.S. House Committee on Science, Space, and Technology Subcommittee on Energy and Subcommittee on Investigations and Oversight},
	author = {Huff, Kathryn D.},
	month = oct,
	year = {2021},
	file = {Huff - 2021 - Testimony of Acting Assistant Secretary Dr. Kathry.pdf:/Users/huff/Zotero/storage/KHJHBXCC/Huff - 2021 - Testimony of Acting Assistant Secretary Dr. Kathry.pdf:application/pdf},
}

@article{bachmann_enrichment_2021,
	title = {Enrichment dynamics for advanced reactor {HALEU} support},
	volume = {7},
	copyright = {{\textcopyright} A. M. Bachmann et al., Published by EDP Sciences, 2021},
	issn = {2491-9292},
	url = {https://www.epj-n.org/articles/epjn/abs/2021/01/epjn210024/epjn210024.html},
	doi = {10.1051/epjn/2021021},
	abstract = {Transitioning to High Assay Low Enriched Uranium-fueled reactors will alter the material requirements of the current nuclear fuel cycle, in terms of the mass of enriched uranium and Separative Work Unit capacity. This work simulates multiple fuel cycle scenarios using Cyclus to compare how the type of the advanced reactor deployed and the energy growth demand affect the material requirements of the transition to High Assay Low Enriched Uranium-fueled reactors. Fuel cycle scenarios considered include the current fleet of Light Water Reactors in the U.S. as well as a no-growth and a 1\% growth transition to either the Ultra Safe Nuclear Corporation Micro Modular Reactor or the X-energy Xe-100 reactor from the current fleet of U.S. Light Water Reactors. This work explored parameters of interest including the number of advanced reactors deployed, the mass of enriched uranium sent to the reactors, and the Separative Work Unit capacity required to enrich natural uranium for the reactors. Deploying Micro Modular Reactors requires a higher average mass and Separative Work Unit capacity than deploying Xe-100 reactors, and a lower enriched uranium mass and a higher Separative Work Unity capacity than required to fuel Light Water Reactors before the transition. Fueling Xe-100 reactors requires less enriched uranium and Separative Work Unit capacity than fueling Light Water Reactors before the transition.},
	language = {en},
	urldate = {2021-12-02},
	journal = {EPJ Nuclear Sciences \& Technologies},
	author = {Bachmann, Amanda M. and Fairhurst-Agosta, Roberto and Richter, Zo{\"e} and Ryan, Nathan and Munk, Madicken},
	year = {2021},
	note = {Publisher: EDP Sciences},
	pages = {22},
	file = {Full Text PDF:/Users/huff/Zotero/storage/FYNRE7KP/Bachmann et al. - 2021 - Enrichment dynamics for advanced reactor HALEU sup.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/WNTQTYM3/epjn210024.html:text/html},
}

@phdthesis{chee_fluoride-salt-cooled_2021,
	address = {Urbana, IL},
	type = {Prelim},
	title = {Fluoride-{Salt}-{Cooled} {High} {Temperature} {Reactor} {Design} {Optimization} with {Evolutionary} {Algorithms}},
	copyright = {Copyright 2021 Gwendolyn Jin Yi Chee},
	abstract = {The nuclear power industry must overcome cost and safety challenges to ensure continued
global use and expansion of nuclear energy technology to provide low-carbon electricity
worldwide. The Generation IV International Forum identi ed six nuclear reactor systems
that promise signi cant advances in safety, sustainability, e ciency, and cost over existing
designs. The Fluoride-Salt-Cooled High-Temperature Reactor (FHR) system, speci cally
the Advanced High Temperature Reactor (AHTR) design, combines the best aspects of two
identi ed Generation IV systems: Molten Salt Reactor (MSR) and Very-High-Temperature
Reactor (VHTR). The AHTR uses the MSR's low-pressure liquid fluoride-salt coolant and
VHTR's high-temperature coated-particle fuel. The AHTR's fuel geometry has triple het-
erogeneity, resulting in complex reactor physics and signi cant modeling challenges. To
further understand and address the technical challenges associated with the AHTR de-
sign, this work proposes participation in the Organisation for Economic Co-operation and
Development-Nuclear Energy Agency's FHR benchmarking exercise by modeling its neutron-
ics and thermal-hydraulics with OpenMC and Moltres nuclear software. In the proposed
work, I will also explore the impact of additive manufacturing technology advancements
on reactor geometry optimization, speci cally for the AHTR design. Leveraging additive
manufacturing technology enables us to surpass classical manufacturing constraints, such as
straight fuel channels or homogenous fuel enrichment, and optimize for arbitrary geometries
and parameters such as non-uniform channel shapes and inhomogeneous fuel distribution
throughout the core. This work proposes to design and demonstrate an optimization tool
that uses the evolutionary algorithm optimization technique with neutron transport and
thermal-hydraulics software to find new optimal reactor geometries enabled by additive
manufacturing technology.},
	school = {University of Illinois at Urbana-Champaign},
	author = {Chee, Gwendolyn J. Y.},
	month = sep,
	year = {2021},
	file = {2021-chee-prelim-pres-09-13.pdf:/Users/huff/Zotero/storage/VEUAGPZV/2021-chee-prelim-pres-09-13.pdf:application/pdf;Chee - 2021 - Fluoride-Salt-Cooled High Temperature Reactor Desi.pdf:/Users/huff/Zotero/storage/6JGMUW4I/Chee - 2021 - Fluoride-Salt-Cooled High Temperature Reactor Desi.pdf:application/pdf},
}

@misc{bachmann_impacts_2022,
	address = {Raleigh, NC},
	title = {Impacts of {HALEU} on the {Nuclear} {Fuel} {Cycle}},
	author = {Bachmann, Amanda},
	month = mar,
	year = {2022},
	file = {Bachmann - 2022 - Impacts of HALEU on the Nuclear Fuel Cycle.pdf:/Users/huff/Zotero/storage/AGV4996A/Bachmann - 2022 - Impacts of HALEU on the Nuclear Fuel Cycle.pdf:application/pdf},
}

@misc{richter_isotopic_2022,
	title = {Isotopic {Fuel} {Compositions} in the {Sangamon200} {Model}},
	url = {https://zenodo.org/record/6426312},
	doi = {10.5281/zenodo.6426312},
	abstract = {The seven csv files each correspond to a different level of fuel burnup in the Sangamon200 (a 200 MWth pebble-bed HTGR) fuel pebbles.~fresh\_comp.csv provides the composition for UCO in fresh pebbles.~1pass\_comp.csv provides the fuel composition in pebbles that have gone through one six month pass, 2pass\_comp.csv have been through two six month passes, and so forth.},
	urldate = {2022-04-11},
	publisher = {Zenodo},
	author = {Richter, Zoe},
	month = apr,
	year = {2022},
	file = {Zenodo Snapshot:/Users/huff/Zotero/storage/9DI4KUEB/6426312.html:text/html},
}

@misc{bachmann_cyclus_2020,
	title = {Cyclus tutorial input and output files},
	url = {https://zenodo.org/record/4557613},
	abstract = {Example input and output files for the tutorial for Cyclus at http://fuelcycle.org/user/tutorial/index.html},
	urldate = {2022-05-25},
	publisher = {Zenodo},
	author = {Bachmann, Amanda and Chee, Gwendolyn and Bae, Jin Whan and Westphal, Gregory and Kennelly, Tyler and Huff, Kathryn},
	month = nov,
	year = {2020},
	doi = {10.5281/zenodo.4557613},
	annote = {This material is based upon work supported under an Integrated University Program Graduate
Fellowship. Any opinions, findings, conclusions or recommendations expressed in this publication are
those of the author(s) and do not necessarily reflect the views of the Department of Energy
Office of Nuclear Energy.},
	file = {Zenodo Snapshot:/Users/huff/Zotero/storage/SV8JQDPV/4557613.html:text/html},
}

@article{park_verification_2022,
	title = {Verification of moltres for multiphysics simulations of fast-spectrum molten salt reactors},
	volume = {173},
	issn = {03064549},
	url = {https://linkinghub.elsevier.com/retrieve/pii/S0306454922001463},
	doi = {10.1016/j.anucene.2022.109111},
	abstract = {Modeling strongly coupled neutronics and thermal{\textendash}hydraulics in liquid-fueled MSRs requires robust and flexible multiphysics software for accurate simulations at reasonable computational costs. In this paper, we present Moltres and its neutronics and thermal{\textendash}hydraulics modeling capabilities relevant to multiphysics reactor analysis. As a MOOSE-based application, Moltres provides various multiphysics coupling schemes and time-stepping methods, including fully coupled solves with implicit time-stepping. We verified Moltres{\textquoteright} MSR modeling capabilities against a multiphysics numerical benchmark developed for software dedicated to modeling fast-spectrum MSRs. The results show that Moltres performed comparably to participating software packages in the benchmark; the majority of the relevant quantities fell within one standard deviation of the benchmark average. Among the participating multiphysics tools in the benchmark, Moltres agrees closest to the multiphysics tool from the Delft University of Technology due to similarities in the numerical solution techniques and meshing schemes.},
	language = {en},
	urldate = {2022-04-26},
	journal = {Annals of Nuclear Energy},
	author = {Park, Sun Myung and Munk, Madicken},
	month = aug,
	year = {2022},
	pages = {109111},
	file = {Park and Munk - 2022 - Verification of moltres for multiphysics simulatio.pdf:/Users/huff/Zotero/storage/PHNTVU4R/Park and Munk - 2022 - Verification of moltres for multiphysics simulatio.pdf:application/pdf},
}

@mastersthesis{richter_isotopic_2022-1,
	address = {Urbana, IL},
	title = {{ISOTOPIC} {AND} {REACTOR} {PHYSICS} {CHARACTERIZATION} {OF} {A} {GAS}-{COOLED}, {PEBBLE}-{BED} {MICROREACTOR}},
	language = {en},
	school = {University of Illinois at Urbana-Champaign},
	author = {Richter, Zo{\"e}},
	month = may,
	year = {2022},
	file = {Richter - ISOTOPIC AND REACTOR PHYSICS CHARACTERIZATION OF A.pdf:/Users/huff/Zotero/storage/R9VDP2FJ/Richter - ISOTOPIC AND REACTOR PHYSICS CHARACTERIZATION OF A.pdf:application/pdf},
}

@phdthesis{chee_fluoride-salt-cooled_2022,
	address = {Urbana, IL},
	type = {Dissertation},
	title = {Fluoride-{Salt}-{Cooled} {High} {Temperature} {Reactor} {Design} {Optimization} with {Evolutionary} {Algorithms}},
	copyright = {Copyright 2021 Gwendolyn Jin Yi Chee},
	url = {https://github.com/arfc/2022-chee-dissertation},
	abstract = {Additive manufacturing of reactor core components removes the geometric constraints required by conventional manufacturing, such as slabs as fuel planks and cylinders as fuel rods. Due to the expansion of the potential design space facilitated through additive manufacturing, reactor designers need to find methods, such as generative design, to explore the design space efficiently. In this defense, I will show that I successfully applied evolutionary algorithms to conduct generative reactor design optimization for a fluoride-salt-cooled high-temperature reactor (FHR). I achieved this through three distinct research efforts: 1) furthering our understanding of the FHR design{\textquoteright}s complexities through neutronics and temperature modeling, 2) creating an open-source tool that enables generative design reactor optimization with evolutionary algorithms, and 3) applying the tool to the FHR to optimize for non-conventional geometries and fuel distributions},
	school = {University of Illinois at Urbana-Champaign},
	author = {Chee, Gwendolyn Jin Yi},
	month = aug,
	year = {2022},
	file = {2022-chee-dissertation-pres.pdf:/Users/huff/Zotero/storage/Y93FYTHR/2022-chee-dissertation-pres.pdf:application/pdf;Chee - 2021 - Fluoride-Salt-Cooled High Temperature Reactor Desi.pdf:/Users/huff/Zotero/storage/EXF7M46A/Chee - 2021 - Fluoride-Salt-Cooled High Temperature Reactor Desi.pdf:application/pdf},
}

@inproceedings{bachmann_sensitivity_2022,
	address = {Phoenix, AZ},
	title = {Sensitivity analysis of fuel cycle transitions using {Cyclus}-{Dakota}},
	booktitle = {Proceedings of the {International} {High} {Level} {Radioactive} {Waste} {Management} {Conference}},
	author = {Bachmann, Amanda M. and Richards, Scott and Munk, Madicken and Feng, Bo},
	month = nov,
	year = {2022},
}

@phdthesis{dotson_influence_2022,
	address = {Urbana, IL},
	type = {Thesis},
	title = {The influence of temporal detail and inter-annual resource variability on energy planning models},
	copyright = {Copyright 2022 Samuel G. Dotson},
	url = {https://hdl.handle.net/2142/115793},
	abstract = {Decarbonizing the United States energy system is a challenging task. The situation is exacerbated by the lack of strong federal climate policy, leaving individual states and institutions to drive the energy sector towards net-zero carbon emissions. ESOM tools use linear programming to develop policy insights that may help achieve full decarbonization. However, there is a widely recognized tradeoff between model complexity and computational cost. Adding spatial, temporal, and technological details make these models more realistic, but may make them computationally intractable. Previously, most ESOM studies prioritize technology options over spatial or temporal detail. This choice emphasizes the role of technology costs, such as fuel and capital costs, on energy policy without considering operational challenges. This thesis uses the ESOM, Temoa to model Illinois{\textquoteright} and the University of Illinois{\textquoteright} energy systems and develops the PyGenesys tool to facilitate sensitivity analysis. The sensitivities considered in this work are temporal resolution and the annual capacity factors of wind and solar energy, or the inter-annual variability.

The results of the time resolution study showed that any temporal aggregation above an hourly level may generate misleading results that minimizes the roles of firm clean power and energy storage. Additionally, the role of wind energy is overestimated in models with less temporal detail, and the roles of solar energy and advanced nuclear reactors are underestimated. The study of inter-annual variability showed that energy systems with majority variable intermittent renewables, such as solar and wind, that exclude clean firm power from nuclear power plants exhibit higher energy costs with nearly 63 times the variance of systems that use a majority of clean firm power. Additionally, the amount of capacity necessary to meet electricity demand is greater and more uncertain in systems with high renewable penetration. Finally, based on the results in each of the sensitivity analyses, this thesis recommends that Illinois continues supporting its existing nuclear fleet with {\textquotedblleft}zero emissions credits{\textquotedblright} and expand clean firm capacity with advanced nuclear reactors by lifting the moratorium on new nuclear builds.},
	language = {en},
	urldate = {2022-11-14},
	school = {University of Illinois Urbana-Champaign},
	author = {Dotson, Samuel G.},
	year = {2022},
	file = {Full Text:/Users/huff/Zotero/storage/6NMTC25J/Dotson - The influence of temporal detail and inter-annual .pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/YB276H8L/124977.html:text/html},
}

@inproceedings{richter_modeling_2023,
	title = {Modeling and {Simulation} of {Xe}-100 type {Pebble}-{Bed} {Gas}-{Cooled} {Reactor} with {SCALE}},
	language = {eng},
	author = {Richter, Zo{\"e} and Davidson, Eva and Skutnik, Steve and Munk, Madicken},
	month = aug,
	year = {2023},
	pages = {10},
	file = {Richter et al. - 2023 - Modeling and Simulation of Xe-100 type Pebble-Bed .pdf:/Users/huff/Zotero/storage/PC4PZEFV/Richter et al. - 2023 - Modeling and Simulation of Xe-100 type Pebble-Bed .pdf:application/pdf},
}

@misc{bachmann_openmcyclus_2023,
	title = {{OpenMCyclus} v0.1.0},
	url = {https://zenodo.org/record/8349474},
	abstract = {Third party archetype for Cyclus to model a reactor facility that is coupled with the stand-alone depletion solver in OpenMC to dynamically update fuel compositions.},
	urldate = {2023-09-19},
	publisher = {Zenodo},
	author = {Bachmann, Amanda M. and Yardas, Olek and Munk, Madicken},
	month = sep,
	year = {2023},
	doi = {10.5281/zenodo.8349474},
	keywords = {depletion, nuclear fuel cycles},
	file = {Zenodo Snapshot:/Users/huff/Zotero/storage/7XQU7XEE/8349474.html:text/html},
}

@misc{bachmann_mmr-like_2023,
	title = {{MMR}-like {Serpent} {Model}},
	url = {https://zenodo.org/record/8349385},
	abstract = {A serpent model designed after the Ultra Safe Nuclear Corporation (USNC) Micro Modular Reactor (MMR) reactor design, based on publicly available information.},
	urldate = {2023-09-19},
	publisher = {Zenodo},
	author = {Bachmann, Amanda},
	month = sep,
	year = {2023},
	doi = {10.5281/zenodo.8349385},
	keywords = {Monte Carlo, Microreactor},
	file = {Zenodo Snapshot:/Users/huff/Zotero/storage/GSCGL36K/8349385.html:text/html},
}

@misc{bae_jbae11ann_pwr_2019,
	title = {jbae11/ann\_pwr: {Zenodo} {Release}},
	shorttitle = {jbae11/ann\_pwr},
	url = {https://zenodo.org/record/3353745},
	abstract = {Cyclus batch-wise reactor module using neural network depletion model},
	urldate = {2023-06-22},
	publisher = {Zenodo},
	author = {Bae, Jin Whan},
	month = jul,
	year = {2019},
	doi = {10.5281/zenodo.3353745},
	file = {Zenodo Snapshot:/Users/huff/Zotero/storage/P5DUWA74/3353745.html:text/html},
}

@misc{rivers_another_2023,
	title = {Another delay at plant {Vogtle}; {New} {Jacksonville} history podcast; {Jax} {PBS} {Kids} {Writers} {Contest}},
	url = {https://news.wjct.org/show/first-coast-connect-with-melissa-ross/2023-02-23/first-coast-connect-plant-vogtle-bygone-jax-podcast},
	abstract = {A nuclear power plant in Georgia delays expansion; {\textquotedblleft}Bygone Jax: Our Unsung History,{\textquotedblright} a new podcast from WJCT Public Media; and the Jax PBS Kids Writers Contest.},
	language = {en},
	urldate = {2023-03-06},
	journal = {WJCT News},
	author = {Rivers, Brendan},
	month = feb,
	year = {2023},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/2A75U39X/first-coast-connect-plant-vogtle-bygone-jax-podcast.html:text/html},
}

@misc{news_12_staff_science_2021,
	title = {Science community comes to defense of student who brought uranium plate to school},
	url = {https://newjersey.news12.com/science-community-comes-to-defense-of-student-who-brought-uranium-plate-to-school},
	abstract = {The science community is coming to the defense of a student who caused school to be evacuated after bringing a plate made with depleted uranium to school.},
	urldate = {2023-03-06},
	journal = {News 12 - New Jersey},
	author = {News 12 Staff},
	month = jan,
	year = {2021},
	file = {Snapshot:/Users/huff/Zotero/storage/R8ZC3LGN/science-community-comes-to-defense-of-student-who-brought-uranium-plate-to-school.html:text/html},
}

@misc{zackowski_season_2021,
	title = {Season 3 {Episode} 29: {Bad} {Bites}, {Cat} {Personalities} and {Amanda} {Bachmann} on {Nuclear} {Science} - {The} {Science} {Pawdcast}},
	shorttitle = {Season 3 {Episode} 29},
	url = {https://bunsenbernerbmd.buzzsprout.com/413041/9245459-season-3-episode-29-bad-bites-cat-personalities-and-amanda-bachman-on-nuclear-science},
	abstract = {This week on The Science Pawdcast we chat about a new study which discovered why small biting insects can use tiny mandibles to do serious damage.~ In Pet Science we chat about a study that concluded some new information about Cat Personalities!~ ...},
	language = {en},
	urldate = {2021-10-07},
	author = {Zackowski, Jason},
	month = sep,
	year = {2021},
	file = {Snapshot:/Users/huff/Zotero/storage/9XAEBIZC/9245459-season-3-episode-29-bad-bites-cat-personalities-and-amanda-bachman-on-nuclear-science.html:text/html},
}

@phdthesis{dotson_towards_2024,
	address = {Champaign, IL},
	type = {Prelim},
	title = {Towards a {Holistic} {Integration} of {Energy} {Justice} and {Energy} {System} {Engineering}},
	copyright = {Copyright 2024 Samuel G. Dotson},
	abstract = {Climate change produced by greater atmospheric CO2 concentrations from human activity has led to
increased exposure to hazards worldwide and domestically: increased storm severity, rising sea levels, more
extreme temperatures, hotter summers, and rising sea levels to name a few. Without immediate action to
reduce carbon emissions, these impacts will worsen. Specifically, it is primarily our societal dependence on
fossil fuels to support our expansive economies and energy systems that contributes the most to rising carbon
dioxide levels (along with other greenhouse gases (GHGs)). Therefore, to achieve the almost universally
shared goal of halting and reversing the effects of climate change, our globalized society must transition
away from fossil fuels to clean energy technologies such as nuclear and renewable energy and switch our
transportation systems to electric or hydrogen powered vehicles.},
	language = {en},
	school = {University of Illinois Urbana-Champaign},
	author = {Dotson, Samuel G.},
	month = jan,
	year = {2024},
	file = {Dotson - 2024 - Towards a Holistic Integration of Energy Justice a.pdf:/Users/huff/Zotero/storage/4DC9JLJL/Dotson - 2024 - Towards a Holistic Integration of Energy Justice a.pdf:application/pdf},
}

@techreport{yardas_full_2024,
	address = {Idaho Falls, ID},
	title = {Full core depletion study for the {Fluoride} {High} {Temperature} {Reactor} ({FHR}) benchmark study},
	institution = {Idaho National Lab},
	author = {Yardas, Oleksandr and Seifert, Luke and Giudicelli, Guillaume L. and Munk, Madicken},
	year = {2024},
	file = {Yaras et al. - 2024 - Full core depletion study for the Fluoride High Te.pdf:/Users/huff/Zotero/storage/YYTH4Q8Y/Yaras et al. - 2024 - Full core depletion study for the Fluoride High Te.pdf:application/pdf},
}

@techreport{yardas_saltproc_2024,
	address = {Idaho Falls},
	title = {{SaltProc} verification with {OpenMC}},
	institution = {Idaho National Lab},
	author = {Yardas, Oleksandr and Giudicelli, Guillaume L. and Munk, Madicken},
	year = {2024},
	file = {Yardas et al. - 2024 - SaltProc verification with OpenMC.pdf:/Users/huff/Zotero/storage/FTL86V2Q/Yardas et al. - 2024 - SaltProc verification with OpenMC.pdf:application/pdf},
}

@phdthesis{yardas_implementation_2023,
	type = {Thesis},
	title = {Implementation and validation of {OpenMC} depletion capabilities in {SaltProc}},
	copyright = {Copyright 2023 Oleksandr Redin Yardas},
	url = {https://hdl.handle.net/2142/121954},
	abstract = {No operating molten salt reactors (MSRs) exist, so we must rely on computer simulations to study this technology. Popular MSR designs to use in simulations include the Molten Salt Breeder Reactor (MSBR), the Molten Salt Reactor Experiment (MSRE), and the Molten Salt Fast Reactor (MSFR). A key process to consider for MSRs is on-line fuel reprocessing and its effect on reactor dynamics. SaltProc is an open source interface code tool that simulates on-line fuel reprocessing when coupled with a depletion-capable transport solver. SaltProc was intended to be usable with any depletion solver, but initially was written with support for Serpent2 exclusively. In this work, the SaltProc codebase was overhauled to simplify coupling to depletion solvers. Support for OpenMC was also added. To ensure that the code maintained existing functionality as well as extended it, the new functionality was validated on a full-core model of the MSBR. The results indicate that keff between OpenMC and Serpent2 differ by +35 pcm at beginning of life and by 700 pcm at the end of the simulation after one year of operation. Additionally, the relative difference of most actinides is less than 2\%. The actinides with smaller concentrations in the fuel tend to have larger relative differences between the two codes. The results for fission products are similar, however, the relative differences are smaller, with most of the fission products having a relative difference no greater than 0.6\%. There are some outliers in the results with very high relative errors, however, these can be attributed to numerical errors. This is significant as this makes SaltProc the first completely open-source tool to flexibly and accurately simulate on-line fuel reprocessing.},
	urldate = {2024-03-26},
	school = {University of Illinois at Urbana-Champaign},
	author = {Yardas, Oleksandr Redin},
	month = oct,
	year = {2023},
	file = {Full Text PDF:/Users/huff/Zotero/storage/DEG5W7AK/Yardas - 2023 - Implementation and validation of OpenMC depletion .pdf:application/pdf},
}

@techreport{chen_enabling_2021,
	title = {Enabling {Load} {Following} {Capability} in the {Transatomic} {Power} {MSR}},
	url = {https://www.osti.gov/biblio/1877339},
	abstract = {This project is dedicated towards designing a fuel processing system that enables liquid-fueled molten salt reactors (MSR) to load follow by removing the dissolved xenon in the fuel salt. As one of the Gen-IV nuclear reactor concepts, the molten salt reactor receives increasing development interests in the recent years. One distinguishing feature of the liquid-fueled molten salt reactor is its improved ability to operate in a load-following mode by including the unique online fission product removal system. Load-following means that the reactor changes its power output based on the demand on the grid. Most of the current operating nuclear reactors have limited load-following ability and operate as the base load on the grid. Due to the rapid increase of solar energy, the requirement on load-following capacity is significantly increased because of the varying power output of the solar panels, yet the traditional load-following capacity is expected to decrease as the decarbonization of the grid continues. Therefore, the ability to perform load-following operation for the nuclear reactors will greatly enhance the resilience of the grid and make nuclear energy more economically competitive. This load-following feature is included in many commercial molten salt reactor designs, such as the designs by Transatomic Power, Terrestrial Energy, and Flibe Energy. Unfortunately, detailed analysis of the fuel processing system for commercial scale MSRs is still lacking, as well as how the fuel processing quantitively impacts the load-following operation. Moreover, experimental data for many of the underlying physics of fuel processing is limited. This project aims to pave the way for the fuel processing technology to advance to the commercial stage by performing combined experimental and simulation research. During the project period, four interconnected aspects of the development of the fuel processing system in liquid-fueled molten salt reactors are investigated. These aspects are the simulation and analysis of the fission product removal system, the fuel cycle simulation, the coupled reactor neutronics and thermal hydraulics transient simulation, and the gaseous fission product removal experiment. Multiphase CFD simulations are performed for components of the processing systems, and simplified air-water experiments are carried out to provide validation data. It is concluded that the CFD simulation can satisfactorily predict the system level performance of the components, and engineering models are constructed based on this success. Fuel cycle analysis is performed for two representative MSR design, the MSBR and the Transatomic Power MSR. Open-source code SaltProc is developed to incorporate the unique fuel processing system of the MSRs. It is concluded that the removal of xenon is essential for load-following operation in thermal spectrum MSR and Molten Salt Breeder Reactor. For the Transatomic Power MSR, the xenon poisoning effect is negligible due to its relatively fast neutron spectrum, though the overall fuel cycle economics still benefits from the removal of xenon. Coupled reactor neutronics and thermal hydraulics transient simulation is performed specifically for the Transatomic Power MSR. It is concluded that the reactor core design could perform power ramping fast enough to satisfy load-following operation. Combining the findings from each aspect, it is concluded that the load-following operation of a thermal neutron MSR is dependent upon the removal of xenon, which could be achieved for a commercial sized reactor using continuous inert gas sparging in a separate system with reasonable dimensions.},
	language = {English},
	number = {DOE-UIUC-0983-1},
	urldate = {2024-05-21},
	institution = {Univ. of Illinois at Urbana-Champaign, IL (United States); Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Chen, Jiaqi and Brooks, Caleb S. and Rykhlevskii, Andrei and T{\"u}rkmen, Mehmet and Huff, Kathryn D. and Lee, Alvin and Kozlowski, Tomasz and Li, Zhen and Heuser, Brent J. and Stubbins, James F.},
	month = dec,
	year = {2021},
	doi = {10.2172/1877339},
	file = {Full Text PDF:/Users/huff/Zotero/storage/TCHXIG2X/Chen et al. - 2021 - Enabling Load Following Capability in the Transato.pdf:application/pdf},
}

@article{thiolliere_impact_2022,
	title = {Impact of fresh fuel loading management in fuel cycle simulators: {A} functionality isolation test},
	volume = {392},
	issn = {0029-5493},
	shorttitle = {Impact of fresh fuel loading management in fuel cycle simulators},
	url = {https://www.sciencedirect.com/science/article/pii/S0029549322001029},
	doi = {10.1016/j.nucengdes.2022.111748},
	abstract = {Fuel cycle simulator development started many years ago by several research and engineering institutions or consulting firms for a wide range of applications. To improve confidence in the results, institutions may be tempted to increase the complexity of their software even if this complexity might not be necessary. On the other hand, some simulators may be used outside their range of validity when used in very specific applications. The FIT (Functionality Isolation Test) project is an international effort devoted to improve the confidence in the data produced by fuel cycle simulation tools. The scientific goal is to determine the optimum level of detail a fuel cycle simulator needs according to the type of study and the required confidence level. The project relies on a wide variety of fuel cycle simulators with a large range of complexity levels. The FIT project consists of isolating the impact of one targeted functionality on fuel cycle simulations. The impact of the functionality is assessed using a set of simple basic exercises specifically designed for this purpose, called {\textquotedblright}functionality isolation.{\textquotedblright} The present work focuses on the impact on simulation results of using a fuel loading model (a relation that links the stock isotopic composition with the fresh fuel fabrication according to the reactor requirements) or a fixed fraction approach (the fresh fuel fissile fraction is fixed and does not depend on the stock isotopic composition). The paper first presents the FIT project. The exercise design is described and results show that using a fuel loading model approach has an important impact on fuel cycle outputs under certain conditions that are described. This result is reinforced by the fact that all fuel cycle simulators used in this exercise provide similar conclusions.},
	urldate = {2024-05-21},
	journal = {Nuclear Engineering and Design},
	author = {Thiolli{\`e}re, N. and Doligez, X. and Halasz, M. and Krivtchik, G. and Merino, I. and Mouginot, B. and Skarbeli, A. V. and Hernandez-Solis, A. and Alvarez-Velarde, F. and Courtin, F. and Druenne, H. and Ernoult, M. and Huff, K. and Szieberth, M. and Vermeeren, B. and Wilson, P.},
	month = jun,
	year = {2022},
	keywords = {FIT project, Fuel Cycle Simulators, Fuel Loading Models, Pressurized Water Reactors, Sodium Fast Reactors},
	pages = {111748},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/RN2CINJ6/S0029549322001029.html:text/html},
}

@incollection{gesing_science_2023,
	title = {Science {Gateways} and {AI}/{ML}: {How} {Can} {Gateway} {Concepts} and {Solutions} {Meet} the {Needs} in {Data} {Science}?},
	isbn = {978-1-83768-108-2},
	shorttitle = {Science {Gateways} and {AI}/{ML}},
	url = {https://www.intechopen.com/chapters/86501},
	abstract = {Science gateways are a crucial component of critical infrastructure as they provide the means for users to focus on their topics and methods instead of the technical details of the infrastructure. They are defined as end-to-end solutions for accessing data, software, computing services, sensors, and equipment specific to the needs of a science or engineering discipline and their goal is to hide the complexity of the underlying infrastructure. Science gateways are often called Virtual Research Environments in Europe and Virtual Labs in Australasia; we consider these two terms to be synonymous with science gateways. Over the past decade, artificial intelligence (AI) and machine learning (ML) have found applications in many different fields in private industry, and private industry has reaped the benefits. Likewise, in the academic realm, large-scale data science applications have also learned to apply public high-performance computing resources to make use of this technology. However, academic and research science gateways have yet to fully adopt the tools of AI. There is an opportunity in the gateways space, both to increase the visibility and accessibility to AI/ML applications and to enable researchers and developers to advance the field of science gateway cyberinfrastructure itself. Harnessing AI/ML is recognized as a high priority by the science gateway community. It is, therefore, critical for the next generation of science gateways to adapt to support the AI/ML that is already transforming many scientific fields. The goal is to increase collaborations between the two fields and to ensure that gateway services are used and are valuable to the AI/ML community. This chapter presents state-of-the-art examples and areas of opportunity for the science gateways community to pursue in relation to AI/ML and some vision of where these new capabilities might impact science gateways and support scientific research.},
	language = {en},
	urldate = {2024-05-21},
	booktitle = {Critical {Infrastructure} - {Modern} {Approach} and {New} {Developments}},
	publisher = {IntechOpen},
	author = {Gesing, Sandra and Pierce, Marlon and Marru, Suresh and Zentner, Michael and Huff, Kathryn and Bradley, Shannon and Cleveland, Sean B. and Brandt, Steven R. and Ramnath, Rajiv and Kee, Kerk and Dahan, Maytal and Mart{\'i}nez, Braulio M. Villegas and Sepulveda, Wilmer Contreras and Mondrag{\'o}n, Jos{\'e} J. S{\'a}nchez},
	month = mar,
	year = {2023},
	doi = {10.5772/intechopen.110144},
	file = {Full Text PDF:/Users/huff/Zotero/storage/P7E39DY2/Gesing et al. - 2023 - Science Gateways and AIML How Can Gateway Concep.pdf:application/pdf},
}

@misc{huff_testimony_2024,
	address = {Washington D.C.},
	title = {Testimony of {Dr}. {Kathryn} {Huff} {Assistant} {Secretary} for {Nuclear} {Energy} {U}.{S}. {Department} of {Energy} {Before} the {U}.{S}. {House} {Committee} on {Oversight} and {Accountability} {Subcommittee} on {Economic} {Growth}, {Energy} {Policy}, and {Regulatory} {Affairs} {U}.{S}. {House} of {Representatives}},
	url = {https://oversight.house.gov/hearing/he-next-generation-empowering-american-nuclear-energy/},
	language = {English},
	publisher = {U.S. House Committee on Oversight and Accountability Subcommittee on Economic Growth, Energy Policy, and Regulatory Affairs},
	author = {Huff, Kathryn D.},
	month = jan,
	year = {2024},
	pages = {6},
	file = {Dr.-Huff-Testimony.pdf:/Users/huff/Zotero/storage/6JK8T2TF/Dr.-Huff-Testimony.pdf:application/pdf},
}

@misc{huff_testimony_2023,
	address = {Room SD-366 of the Dirksen Senate Office Building in Washington, DC.},
	title = {Testimony of {Dr}. {Kathryn} {Huff} {Assistant} {Secretary} for {Nuclear} {Energy} {U}.{S}. {Department} of {Energy} {Before} the {U}.{S}. {Senate} {Committee} on {Energy} and {Natural} {Resources} {Full} {Committee} {Hearing} to {Examine} the {Nuclear} {Fuel} {Cycle}},
	url = {https://www.energy.senate.gov/hearings/2023/3/full-committee-hearing-to-examine-the-nuclear-fuel-cycle},
	abstract = {The purpose of this hearing is to examine the nuclear fuel cycle.},
	language = {English},
	publisher = {U.S. Senate Committee on Natural Resources},
	author = {Huff, Kathryn D.},
	month = mar,
	year = {2023},
	pages = {4},
	file = {EE5F975E-30A7-4075-9177-3A220627CC36.pdf:/Users/huff/Zotero/storage/DAZRTWHX/EE5F975E-30A7-4075-9177-3A220627CC36.pdf:application/pdf;Witness List 3-9-23 SENR Cmte Hrg.pdf:/Users/huff/Zotero/storage/YZSZGDGW/Witness List 3-9-23 SENR Cmte Hrg.pdf:application/pdf},
}

@misc{huff_testimony_2022,
	address = {Washington D.C.},
	title = {Testimony of {Dr}. {Kathryn} {Huff} {Assistant} {Secretary} for {Nuclear} {Energy} and {Douglas} {MacIntyre} {Deputy} {Director} for the {Office} of {Petroleum} {Reserves} {U}.{S}. {Department} of {Energy}},
	shorttitle = {Full {Committee} {Hearing} {To} {Consider} {Pending} {Legislation}},
	url = {https://www.energy.senate.gov/hearings/2022/12/full-committee-hearing-to-consider-pending-legislation},
	abstract = {The purpose of this hearing is to receive testimony on the following bills:

S. 3112, to amend the Energy Policy Act of 2005 to establish a Hydrogen Technologies for Heavy Industry Grant Program, and for other purposes (Hydrogen for Industry Act of 2021);
S. 3152, to amend the Energy Policy Act of 2005 to disqualify certain borrowers from receiving a guarantee for a project, and for other purposes;
S. 3915, to require the Secretary of Energy to provide technology grants to strengthen domestic mining education, and for other purposes (Mining Schools Act of 2022);
S. 3957, to amend the Infrastructure Investment and Jobs Act to make certain activities eligible for grants from the Abandoned Mine Reclamation Fund, and for other purposes (STREAM Act);
S. 3978, to require the Secretary of Energy to carry out a program to operate a uranium reserve consisting of uranium produced and converted in the United States and a program to ensure the availability of uranium produced, converted, and enriched in the United States, and for other purposes (NO RUSSIA Act of 2022);
S. 4420, to provide for advancements in carbon removal research, quantification, and commercialization, including by harnessing natural processes, and for other purposes (CREST Act of 2022);
S. 4424, to amend the Recreation and Public Purposes Act to authorize sales and leases of certain Federal land to federally recognized Indian Tribes, and for other purposes (Recreation and Public Purposes Tribal Parity Act);
S. 4515, to require the Secretary of Energy to stipulate, as a condition on the sale at auction of any crude oil from the Strategic Petroleum Reserve, that the crude oil not be exported to certain countries, and for other purposes (No Emergency Crude Oil for Foreign Adversaries Act);
S. 4542, to establish the Dolores River National Conservation Area and the Dolores River Special Management Area in the State of Colorado, to protect private water rights in the State, and for other purposes (Dolores River National Conservation Area and Special Management Area Act);
S. 4579,  to amend the Energy and Water Development and Related Agencies Appropriations Act, 2015, to extend certain deadlines applicable to pilot projects to increase Colorado River System water to address effects of historic drought conditions, and for other purposes (Colorado River Basin Conservation Act);
S. 4651, to amend the Energy Policy and Conservation Act to require the Secretary of Energy to stipulate, as a condition on the sale at auction of any petroleum products from the Strategic Petroleum Reserve, that the petroleum products not be exported to certain countries, to prohibit such sales to certain state-owned entities, and for other purposes;
S. 4732, to authorize the Georgetown African American Historic Landmark Project and Tour to establish a commemorative work in the District of Columbia and its environs, and for other purposes (Enslaved Voyages Memorial Act);  
S. 4860, to provide for the establishment of a grazing management program on Federal land in Malheur County, Oregon, and for other purposes (Malheur Community Empowerment for the Owhyee Act); 
S. 4995, to require the Secretary of Agriculture and the Secretary of the Interior to prioritize the completion of the Continental Divide National Scenic Trail, and for other purposes (Continental Divide Trail Completion Act);
S. 5129, to modify the boundary of the Mammoth Cave National Park in the State of Kentucky;
S.\_\_\_, discussion draft to establish a new organization to manage nuclear waste, provide a consensual process for siting nuclear waste facilities, ensure adequate funding for managing nuclear water, and for other purposes (Nuclear Waste Administration Act); and
S.J. Res. 62, approving the location of a memorial to commemorate the commitment of the United States to a free press by honoring journalists who sacrificed their lives in service to that cause.},
	language = {English},
	publisher = {U.S. Senate Committee on Energy and Natural Resources},
	author = {Huff, Kathryn D. and MacIntyre, Douglas},
	month = dec,
	year = {2022},
	pages = {7},
	file = {Huff and MacIntyre - 2022 - Testimony of Dr. Kathryn Huff Assistant Secretary .pdf:/Users/huff/Zotero/storage/UEU29AKJ/Huff and MacIntyre - 2022 - Testimony of Dr. Kathryn Huff Assistant Secretary .pdf:application/pdf;Witness List 12-1-22 SENR Cmte Hrg.pdf:/Users/huff/Zotero/storage/4GP26JKU/Witness List 12-1-22 SENR Cmte Hrg.pdf:application/pdf},
}

@misc{huff_testimony_2022-1,
	address = {Room SD-366 of the Dirksen Senate Office Building in Washington, DC.},
	title = {Testimony of {Dr}. {Kathryn} {Huff} {Assistant} {Secretary} for {Nuclear} {Energy} and {Ms}. {Kelly} {Speakes}-{Backman} {Principal} {Deputy} {Assistant} {Secretary} for {Energy} {Efficiency} and {Renewable} {Energy} {U}.{S}. {Department} of {Energy} {Before} the {Committee} on {Energy} and {Natural} {Resources} {U}.{S}. {Senate}},
	url = {https://www.energy.senate.gov/hearings/2022/7/full-committee-hearing-to-consider-pending-legislation},
	abstract = {The purpose of this hearing is to receive testimony on the following bills:

S. 3145, to amend the Natural Gas Act to expedite approval of exports of small volumes of natural gas, and for other purposes (Cassidy, Kennedy, Inhofe, Rubio, Scott);
S. 3543, to support research, development, and other activities to develop innovative vehicle technologies, and for other purposes (Peters, Hagerty, Stabenow);
S. 3719, to establish the Southwestern Power Administration Fund, and for other purposes (Moran, Marshall);
S. 3740, to provide for a comprehensive and integrative program to accelerate microelectronics research and development at the Department of Energy, and for other purposes (Kelly, Blackburn);
S. 3769, to amend the Energy Conservation and Production Act to improve the weatherization assistance program, and for other purposes (Reed, Collins, Coons, Shaheen);
S. 3856, to prohibit the importation of uranium from the Russian Federation (Barrasso, Lummis, Marshall, Cramer, Hoeven, Capito, Rubio);
S. 4038, to increase the production and use of renewable diesel and sustainable aviation fuel, and for other purposes (Barrasso, Feinstein, Cassidy, Lujan, Daines);
S. 4061, to amend the Energy Policy and Conservation Act to modify the definition of water heater under energy conservation standards, and for other purposes (Stabenow, Blackburn, Hirono);
S. 4066, to amend the Energy Act of 2020 to require the Secretary of Energy to establish a program to accelerate the availability of commercially produced high-assay, low-enriched uranium in the United States and to make high-assay, low-enriched uranium produced from Department of Energy inventories available for use in advanced nuclear reactors, and for other purposes (Barrasso);
S. 4280, to require the Secretary of Energy to remove carbon dioxide directly from ambient air or seawater, and for other purposes (Coons, Whitehouse)},
	language = {English},
	publisher = {U.S. Senate Committee on Natural Resources},
	author = {Huff, Kathryn D. and Speakes-Backman, Kelly},
	month = jul,
	year = {2022},
	pages = {8},
	file = {Huff and Speakes-Backman - 2022 - Testimony of Dr. Kathryn Huff Assistant Secretary .pdf:/Users/huff/Zotero/storage/2LUCXART/Huff and Speakes-Backman - 2022 - Testimony of Dr. Kathryn Huff Assistant Secretary .pdf:application/pdf},
}

@article{turkmen_machine_2021,
	title = {Machine learning application to single channel design of molten salt reactor},
	volume = {161},
	issn = {0306-4549},
	url = {https://www.sciencedirect.com/science/article/pii/S0306454921002851},
	doi = {10.1016/j.anucene.2021.108409},
	abstract = {This study proposes a robust approach to quickly design a nuclear reactor core and explores the best performing machine learning (ML) technique for predicting feature parameters of the core. We implemented the approach into a hypothetical channel of molten salt reactors to demonstrate the applicability of the method. We prepared a Python tool, named Plankton, which couples to a reactor physics code and an optimization tool, and imports ML methods. The tool performs three consecutive phases: reactor database generation, machine learning application, and design optimization. We identified the extra trees method as the best performing estimator. With the estimator, we found nine optimum designs in total, one for each fuel-salt pair, and estimated all the performance metrics of the designs with a {\textless}5\% prediction error compared to their actual values. U-Pu-NaCl fuel-salt gave promising results with the highest conversion ratio, the most negative feedback coefficient, and the lowest fast flux.},
	urldate = {2024-05-23},
	journal = {Annals of Nuclear Energy},
	author = {Turkmen, Mehmet and Chee, Gwendolyn J. Y. and Huff, Kathryn D.},
	month = oct,
	year = {2021},
	keywords = {Simulation, Monte Carlo, Optimization, Molten salt reactor, Machine learning, Channel design},
	pages = {108409},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/NANVBD82/S0306454921002851.html:text/html},
}

@misc{huff_testimony_2022-2,
	address = {Washington D.C.},
	title = {Testimony and {Questions} for the {Record} of {Dr}. {Kathryn} {Huff} {Acting} {Assistant} {Secretary} for {Nuclear} {Energy} {U}.{S}. {Department} of {Energy} {Before} the {U}.{S}. {Senate} {Committee} on {Energy} and {Natural} {Resources} {Hearing} to {Consider} the {Nomination} of {Dr}. {Kathryn} {Huff} to be an {Assistant} {Secretary} of {Energy} for {Nuclear} {Energy}},
	shorttitle = {Hearing to {Consider} the {Nomination} of {Dr}. {Kathryn} {Huff} to be an {Assistant} {Secretary} of {Energy} for {Nuclear} {Energy}},
	url = {https://www.energy.senate.gov/hearings/2022/3/hearing-to-consider-the-nomination-of-kathryn-huff-to-be-an-assistant-secretary-of-energy-for-nuclear-energy},
	abstract = {The purpose of the hearing is to consider the nomination of Dr. Kathryn Huff to be an Assistant Secretary of Energy (Nuclear Energy).},
	language = {English},
	publisher = {United States Senate Committee on Energy and Natural Resources},
	author = {Huff, Kathryn D.},
	month = mar,
	year = {2022},
	pages = {6},
	file = {CHRG-117shrg47893.pdf:/Users/huff/Zotero/storage/TA7VSBBM/CHRG-117shrg47893.pdf:application/pdf;Huff - 2022 - Testimony of Dr. Kathryn Huff Acting Assistant Sec.pdf:/Users/huff/Zotero/storage/XKAMT8DW/Huff - 2022 - Testimony of Dr. Kathryn Huff Acting Assistant Sec.pdf:application/pdf;Huff Final Responses to QFRs 3-17-22 SENR Cmte Hrg.pdf:/Users/huff/Zotero/storage/MN47JFUW/Huff Final Responses to QFRs 3-17-22 SENR Cmte Hrg.pdf:application/pdf;Huff Testimony 3-17-22 SENR Cmte Hrg.pdf:/Users/huff/Zotero/storage/J948M5WG/Huff Testimony 3-17-22 SENR Cmte Hrg.pdf:application/pdf},
}

@article{anderson_cyclus_2024,
	title = {Cyclus v1.6.0},
	url = {https://figshare.com/articles/software/Cyclus_v1_6_0/25752558},
	doi = {10.6084/m9.figshare.25752558.v1},
	abstract = {Release 1.6.0 of the Cyclus Project:

Cyclus is the next-generation agent-based nuclear fuel cycle simulator, providing flexibility to users and developers through a dynamic resource exchange solver and plug-in, user-developed agent framework.

The goal of Cyclus is to enable a broad spectrum of fuel cycle simulation while providing a low barrier to entry for new users and agent developers. Cyclus engages with potential module developers and encourages them to join a vibrant community in an expanding ecosystem. Users and developers are always welcome and encouraged to use or contribute to the Cyclus project.},
	journal = {Figshare},
	author = {Anderson, Aaron and Bachmann, Amanda and Bae, Jin Whan and Bhosale, Aditya and Bormann, Lewin and Caldwell-Overdier, Anna and Chandan, Snehal and Chee, Gwendolyn and Flanagan, Robert and Hodge, Ryan and Huff, Kathryn and Kleimenhagen, Kip and Krueger, Dean and McGarry, Meghan and Mouginot, Baptiste and Mummah, Kathryn and Nibbelink, Ben and Park, Gyutae and Redfoot, Emma and Robert, Yves and Schalz, Max and Scopatz, Anthony and Stomps, Jordan and Wang, Di and Wilson, Paul},
	month = may,
	year = {2024},
}

@misc{tinker_energy_2023,
	address = {Austin, TX, United States},
	title = {Energy {Switch} {\textbar} {Nuclear} {Waste} {\textbar} {Season} 3 {\textbar} {Episode} 1 {\textbar} {PBS}},
	url = {https://www.pbs.org/video/nuclear-waste-h5oay7/},
	abstract = {What should we do about nuclear waste? Experts explore possible solutions.},
	language = {en},
	urldate = {2024-05-23},
	journal = {Energy Switch},
	publisher = {PBS},
	author = {Tinker, Scott},
	month = oct,
	year = {2023},
	file = {Snapshot:/Users/huff/Zotero/storage/NY4C9EL7/nuclear-waste-h5oay7.html:text/html},
}

@article{gearino_meet_2023,
	title = {Meet the {Millennial} {Scientist} {Leading} the {Biden} {Administration}{\textquoteright}s {Push} for a {Nuclear} {Power} {Revival}},
	volume = {Inside Clean Energy},
	url = {https://insideclimatenews.org/news/16022023/inside-clean-energy-kathryn-huff-nuclear-energy/},
	abstract = {Kathryn Huff grew up in Bellville, Texas, a city of about 4,200 residents in the rural area west of Houston, and discovered at a young age that she had an aptitude for math. She remembers the moment that she toured the Texas A\&M University nuclear research reactor and saw Cherenkov radiation, which gives off a [{\textellipsis}]},
	language = {en-US},
	number = {February 2023},
	urldate = {2024-05-23},
	journal = {Inside Climate News},
	author = {Gearino, Dan},
	month = feb,
	year = {2023},
	note = {(Republished at Fast Company as "This 36-year-old scientist is leading the Biden administration{\textquoteright}s push for nuclear power")},
	file = {Snapshot:/Users/huff/Zotero/storage/MTWHXPJ3/inside-clean-energy-kathryn-huff-nuclear-energy.html:text/html},
}

@misc{clay_four-part_2021,
	type = {News {Blog}},
	title = {Four-{Part} {Nuclear} {Energy} {Showcase} on {Tomorrow}'s {World} {Today} {Begins} {Saturday}, {October} 23},
	url = {https://www.newswire.com/news/four-part-nuclear-energy-showcase-on-tomorrows-world-today-begins-21531205},
	abstract = {Tune in to Tomorrow's World Today as we speak with top experts to explore the past, present, and future of nuclear energy.},
	language = {en},
	urldate = {2024-05-23},
	journal = {Newswire},
	author = {Clay, Elizabeth},
	month = oct,
	year = {2021},
	file = {Snapshot:/Users/huff/Zotero/storage/MH8SHK8J/four-part-nuclear-energy-showcase-on-tomorrows-world-today-begins-21531205.html:text/html},
}

@misc{taylor_clean_2021,
	title = {The {Clean} {Factor}: {Part} {One} of a {Tomorrow}'s {World} {Today} {Four} {Part} {Exploration}},
	url = {https://www.tomorrowsworldtoday.com/videos/s4e08-the-clean-factor/},
	abstract = {In part one of this four-part exploration, George sends Greg to the field to discover how Nuclear Energy is helping us reach our goal of a zero-carbon footprint by 2050.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {TOMORROW{\textquoteright}S WORLD TODAY{\textregistered}},
	publisher = {Science Channel},
	author = {Taylor, Julian V.},
	collaborator = {Davison, George and Costatino, Greg},
	month = oct,
	year = {2021},
	file = {Snapshot:/Users/huff/Zotero/storage/F4PTSFFP/s4e08-the-clean-factor.html:text/html},
}

@misc{huff_farewell_2024,
	title = {Farewell {Interview}: {Assistant} {Secretary} for {Nuclear} {Energy} {Katy} {Huff}},
	shorttitle = {Farewell {Interview}},
	url = {https://www.energy.gov/ne/articles/farewell-interview-assistant-secretary-nuclear-energy-katy-huff},
	abstract = {Assistant Secretary for Nuclear Energy Dr. Kathryn Huff reflects on her time at the U.S. Department of Energy.},
	language = {en},
	urldate = {2024-05-23},
	author = {Huff, Kathryn},
	month = may,
	year = {2024},
	file = {Snapshot:/Users/huff/Zotero/storage/PX2K8EX3/farewell-interview-assistant-secretary-nuclear-energy-katy-huff.html:text/html},
}

@article{portuondo_top_2024,
	title = {Top {DOE} nuclear energy official heads for the exit},
	url = {https://www.eenews.net/articles/top-doe-nuclear-energy-official-heads-for-the-exit/},
	abstract = {Kathryn Huff plans to leave in May after years of leading the federal government's work on advanced reactors and nuclear waste.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {E\&E News by POLITICO},
	author = {Portuondo, Nico},
	month = apr,
	year = {2024},
	file = {Snapshot:/Users/huff/Zotero/storage/EJJ4UFVM/top-doe-nuclear-energy-official-heads-for-the-exit.html:text/html},
}

@article{hsu_uncommon_2023,
	address = {Chicago, IL},
	chapter = {Uncommon Interview},
	title = {Uncommon {Interview}: {Assistant} {Secretary} for the {Office} of {Nuclear} {Energy} {Dr}. {Kathryn} {Huff}},
	shorttitle = {Uncommon {Interview}},
	url = {https://chicagomaroon.com/40245/news/uncommon-interview-assistant-secretary-for-the-office-of-nuclear-energy-dr-kathryn-huff/},
	abstract = {With Hollywood blockbuster Oppenheimer reigniting fascination in all-things-nuclear, The Maroon~sat down with Assistant Secretary of the Office of Nuclear Energy Dr. Kathryn Huff (A.B. {\textquoteright}08) to speak about her background, what she hopes to accomplish during her tenure in the Biden administration, and how the University helped shape who she is today. Huff currently serves...},
	language = {en, sv},
	urldate = {2024-05-23},
	journal = {Chicago Maroon},
	author = {Hsu, Derek},
	month = oct,
	year = {2023},
	note = {Section: News},
	file = {Snapshot:/Users/huff/Zotero/storage/ZPY2E8HM/uncommon-interview-assistant-secretary-for-the-office-of-nuclear-energy-dr-kathryn-huff.html:text/html},
}

@misc{wolfe_top_2024,
	type = {Online {Magazine}},
	title = {Top {U}.{S}. nuclear energy official to step down},
	url = {https://www.power-eng.com/nuclear/top-u-s-nuclear-energy-official-to-step-down/},
	abstract = {Huff began working for the DOE in 2021 as the principal deputy assistant secretary for Nuclear Energy, before performing her current role for one year.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {Power Engineering},
	author = {Wolfe, Sean},
	month = apr,
	year = {2024},
	file = {Snapshot:/Users/huff/Zotero/storage/Z7DFQ8HY/top-u-s-nuclear-energy-official-to-step-down.html:text/html},
}

@article{leone_huff_2024,
	title = {Huff to leave {Department} of {Energy} {May} 3},
	volume = {17},
	url = {https://live-exchangemonitor.pantheonsite.io/huff-to-leave-department-of-energy-may-3-2/},
	abstract = {Kathryn Huff will leave the Department of Energy on May 3, only days before what would have concluded her third year at the top of the Office of Nuclear},
	language = {en-US},
	number = {16},
	urldate = {2024-05-23},
	journal = {ExchangeMonitor: RadWaste Monitor},
	author = {Leone, Dan},
	month = apr,
	year = {2024},
	file = {Snapshot:/Users/huff/Zotero/storage/4RYIDCZY/huff-to-leave-department-of-energy-may-3-2.html:text/html},
}

@misc{edwards_top_2023,
	type = {University},
	title = {Top {U}.{S}. nuclear energy official speaks with {Missouri} {S}\&{T} community},
	url = {https://news.mst.edu/2023/10/top-u-s-nuclear-energy-official-speaks-with-missouri-st-community/},
	abstract = {Last week was Nuclear Science Week, and Missouri University of Science and Technology hosted several events to promote nuclear energy {\textemdash} including having the United States{\textquoteright} top official for nuclear energy speak to the campus community.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {Missouri S\&T University News and Events},
	author = {Edwards, Greg},
	month = oct,
	year = {2023},
	note = {Section: College of Engineering and Computing},
	file = {Snapshot:/Users/huff/Zotero/storage/EEWNQ5HX/top-u-s-nuclear-energy-official-speaks-with-missouri-st-community.html:text/html},
}

@misc{smith_nuclear_2024,
	address = {Washington D.C.},
	title = {A {Nuclear} {Comeback}: {Are} {New} {Reactors} the {Answer}?},
	shorttitle = {A {Nuclear} {Comeback}},
	url = {https://a16z.com/podcast/a-nuclear-comeback-are-new-reactors-the-answer/},
	abstract = {Nuclear energy accounts for 20\% of the electricity in the United States, but remarkably, 2023 marked the commissioning of the U.S.{\textquoteright}s first new nuclear reactor in over three decades. The past few years have been a story of changing public opinion, but equally, innovative startups crafting groundbreaking reactor designs and an ambitious announcement by the...},
	language = {en},
	urldate = {2024-05-23},
	journal = {A16z},
	publisher = {Andreesen Horowitz},
	author = {Smith, Steph},
	collaborator = {Huff, Kathryn and Ulevitch, David and Bernauer, Doug},
	month = mar,
	year = {2024},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/TY6CGFGV/a-nuclear-comeback-are-new-reactors-the-answer.html:text/html},
}

@misc{oecd-nea_nuclear_2023,
	type = {Government},
	title = {Nuclear {Energy} {Agency} welcomes {Assistant} {Secretary} {Huff}{\textquoteright}s announcement on the {United} {States}{\textquoteright} decision to join the {NEA} {Data} {Bank}},
	url = {https://www.oecd-nea.org/jcms/pl_84133/nuclear-energy-agency-welcomes-assistant-secretary-huff-s-announcement-on-the-united-states-decision-to-join-the-nea-data-bank},
	abstract = {Nuclear Energy Agency Welcomes Assistant Secretary Huff{\textquoteright}s Announcement on the United States{\textquoteright} Decision to Join the NEA Data Bank},
	language = {en},
	urldate = {2024-05-23},
	journal = {Nuclear Energy Agency (NEA)},
	author = {{OECD-NEA}},
	month = aug,
	year = {2023},
	file = {Snapshot:/Users/huff/Zotero/storage/JF9WE5AR/nuclear-energy-agency-welcomes-assistant-secretary-huff-s-announcement-on-the-united-states-dec.html:text/html},
}

@misc{vakarelska_us_2024,
	title = {{US} / {Officials} {Say} {Government} {Needs} {To} {Take} {Heat} {Off} {First}-{Of}-{Kind} {SMR}},
	url = {https://www.nucnet.org/news/officials-say-government-needs-to-take-heat-off-first-of-kind-smr-2-2-2024},
	abstract = {We need first project to succeed, says DOE assistant secretary},
	urldate = {2024-05-23},
	journal = {The Independent Global Nuclear News Agency},
	author = {Vakarelska, Rumyana},
	month = feb,
	year = {2024},
	file = {Snapshot:/Users/huff/Zotero/storage/9E8FY7DR/officials-say-government-needs-to-take-heat-off-first-of-kind-smr-2-2-2024.html:text/html},
}

@misc{shaw_us_2024,
	title = {{US} ready to replace {Russian} uranium imports, official says},
	url = {https://www.power-technology.com/news/us-ready-to-replace-russian-uranium-following-ban/},
	abstract = {Domestic capacity will be constructed and alternative supplies derived from allies.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {Power Technology},
	author = {Shaw, Alfie},
	month = may,
	year = {2024},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/H98X7RX5/us-ready-replace-russian-uranium-134303827.html:text/html},
}

@article{nelson_doe_2023,
	address = {Idaho Falls, ID},
	title = {{DOE} looking to lease {INL} land to private developers for clean energy projects},
	url = {https://www.eastidahonews.com/2023/10/doe-looking-to-lease-inl-land-to-private-developers-for-clean-energy-projects/},
	abstract = {The U.S. Department of Energy is looking for companies to lease land at the Idaho National Laboratory for the development of clean energy.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {East Idaho News},
	author = {Nelson, Rett},
	month = oct,
	year = {2023},
	file = {Snapshot:/Users/huff/Zotero/storage/KBL6QBH9/doe-looking-to-lease-inl-land-to-private-developers-for-clean-energy-projects.html:text/html},
}

@misc{dalton_cop28_2023,
	title = {Cop28 / {Sapporo} 5 {Leaders} {Announce} \$4.2 {Billion} {Investment} {In} {Uranium} {Market} {\textquoteleft}{Free} {From} {Russian} {Influence}{\textquoteright}},
	url = {https://www.nucnet.org/news/sapporo-5-leaders-announce-usd4-2-billion-investment-in-uranium-market-free-from-russian-influence-12-4-2023},
	abstract = {Move follows pledge by 22 nations to triple nuclear energy capacity by 2050},
	urldate = {2024-05-23},
	journal = {The Independent Global Nuclear News Agency},
	author = {Dalton, David},
	month = dec,
	year = {2023},
	file = {Snapshot:/Users/huff/Zotero/storage/LTFMP3CS/sapporo-5-leaders-announce-usd4-2-billion-investment-in-uranium-market-free-from-russian-influe.html:text/html},
}

@misc{oecd-nea_focusing_2023,
	title = {Focusing on the clean energy transition through a youth lens at {CEM14}},
	url = {https://www.oecd-nea.org/jcms/pl_83770/focusing-on-the-clean-energy-transition-through-a-youth-lens-at-cem14},
	abstract = {The NEA participated in the 14th Clean Energy Ministerial in Goa, India.},
	language = {en},
	urldate = {2024-05-23},
	journal = {Nuclear Energy Agency (NEA)},
	author = {{OECD-NEA}},
	month = jul,
	year = {2023},
	file = {Snapshot:/Users/huff/Zotero/storage/52HRCI5K/focusing-on-the-clean-energy-transition-through-a-youth-lens-at-cem14.html:text/html},
}

@misc{huff_advanced_2023,
	address = {Washington D.C.},
	type = {Panel},
	title = {Advanced {Nuclear} {Energy}: {Opportunities} and {Challenges}},
	shorttitle = {Advanced {Nuclear} {Energy}},
	url = {https://carnegiescience.edu/advanced-nuclear-energy-opportunities-and-challenges},
	abstract = {Join us on Thursday, September 14, 2023, for an expert panel discussion on the deployment of advanced nuclear reactors.},
	language = {en},
	urldate = {2024-05-23},
	author = {Huff, Kathryn and Freed, Joshua and Gershuny, Greg},
	month = sep,
	year = {2023},
	file = {Snapshot:/Users/huff/Zotero/storage/B5G67KWT/advanced-nuclear-energy-opportunities-and-challenges.html:text/html},
}

@misc{tass_russia_2024,
	type = {Russian {News} {Agency}},
	title = {Russia bans entry to 227 {US} citizens involved in {Washington}'s {Russophobic} agenda {\textemdash} {MFA}},
	url = {https://tass.com/politics/1759515},
	abstract = {The ministry specified that the entry ban applies to specific individuals in the executive branch, the business community, the media and academic circles, "who are regularly involved in hostile attacks or the spread of fabrications and outright slander about Russia{\textquoteright}s foreign and domestic policies"},
	urldate = {2024-05-23},
	journal = {TASS},
	author = {{TASS}},
	month = mar,
	year = {2024},
	file = {Snapshot:/Users/huff/Zotero/storage/7VABA25V/1759515.html:text/html},
}

@article{bulowski_canada_2023,
	address = {Vancouver, British Columbia},
	chapter = {News, Politics},
	edition = {May 17, 2023},
	title = {Canada and {U}.{S}. team up to tackle nuclear waste},
	url = {https://www.nationalobserver.com/2023/05/17/news/canada-us-team-tackle-nuclear-waste},
	abstract = {The organization responsible for managing Canada{\textquoteright}s nuclear waste and the U.S. Department of Energy have pledged to work together on the long-term storage of spent nuclear fuel.},
	language = {en},
	urldate = {2024-05-23},
	journal = {Canada's National Observer},
	author = {Bulowski, Natasha},
	month = may,
	year = {2023},
	note = {Section: News},
	file = {Snapshot:/Users/huff/Zotero/storage/T47IH8QM/canada-us-team-tackle-nuclear-waste.html:text/html},
}

@misc{khatib_us_2023,
	type = {News {Website}},
	title = {{US} {Department} of {Energy} representative visits {Barakah} {Nuclear} {Energy} {Plant}},
	url = {https://economymiddleeast.com/news/barakah-nuclear-energy-plant/},
	abstract = {Dr. Kathryn Huff, Assistant Secretary for Nuclear Energy at the U.S. Department of Energy, visited the Barakah Nuclear Energy Plant},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {Economy Middle East},
	author = {Khatib, Hadi},
	month = may,
	year = {2023},
	file = {Snapshot:/Users/huff/Zotero/storage/Y2CC9939/barakah-nuclear-energy-plant.html:text/html},
}

@article{rapier_ensuring_2022,
	title = {Ensuring {A} {Safe} {Future} {For} {Nuclear} {Power}},
	url = {https://www.forbes.com/sites/rrapier/2022/09/12/ensuring-a-safe-future-for-nuclear-power/},
	abstract = {The world needs nuclear power, but can't afford serious nuclear accidents. Here are some of the innovations ensuring those accidents don't happen.},
	language = {en},
	urldate = {2024-05-23},
	journal = {Forbes},
	author = {Rapier, Robert},
	month = sep,
	year = {2022},
	note = {Section: Energy},
}

@article{rapier_nuclear_2022,
	title = {Nuclear {Waste} {And} {The} {Path} {Forward}},
	url = {https://www.forbes.com/sites/rrapier/2022/09/22/nuclear-waste-and-the-path-forward/},
	abstract = {If nuclear power is to expand in the U.S., the problem of nuclear waste has to be addressed. I discuss potential solutions here.},
	language = {en},
	urldate = {2024-05-23},
	journal = {Forbes},
	author = {Rapier, Robert},
	month = sep,
	year = {2022},
	note = {Section: Energy},
	file = {Snapshot:/Users/huff/Zotero/storage/FAHYVJXZ/nuclear-waste-and-the-path-forward.html:text/html},
}

@article{rapier_world_2022,
	title = {The {World} {Won}{\textquoteright}t {Get} {To} {Net} {Zero} {Emissions} {Without} {Nuclear} {Power}},
	url = {https://www.forbes.com/sites/rrapier/2022/08/31/the-world-wont-get-to-net-zero-emissions-without-nuclear-power/},
	abstract = {If the world is going to achieve net zero emissions, we are going to need nuclear power to help us get there.},
	language = {en},
	urldate = {2024-05-23},
	journal = {Forbes},
	author = {Rapier, Robert},
	month = aug,
	year = {2022},
	note = {Section: Energy},
	file = {Snapshot:/Users/huff/Zotero/storage/DA53BIA6/the-world-wont-get-to-net-zero-emissions-without-nuclear-power.html:text/html},
}

@misc{doe_q_2021,
	type = {Government},
	title = {Q\&{A}: {Acting} {Assistant} {Secretary} {Dr}. {Kathryn} {Huff} {Shares} {Her} {Vision} for the {Future} of {Nuclear} {Energy}},
	shorttitle = {Q\&{A}},
	url = {https://www.energy.gov/ne/articles/qa-acting-assistant-secretary-dr-kathryn-huff-shares-her-vision-future-nuclear-energy},
	abstract = {Dr. Kathryn Huff is the new Principal Deputy Assistant Secretary and Acting Assistant Secretary in the Office of Nuclear Energy shares her vision for nuclear energy.},
	language = {en},
	urldate = {2024-05-23},
	journal = {Energy.gov},
	author = {{DOE}},
	collaborator = {Huff, Kathryn},
	month = jun,
	year = {2021},
	file = {Snapshot:/Users/huff/Zotero/storage/3TCMUAUJ/qa-acting-assistant-secretary-dr-kathryn-huff-shares-her-vision-future-nuclear-energy.html:text/html},
}

@misc{forrest_u_2021,
	type = {University},
	title = {U of {I} engineering professor appointed to {US} {Department} of {Energy} leadership role},
	url = {https://news.illinois.edu/view/6367/1199806555},
	abstract = {Kathryn Huff has accepted an appointment as principal deputy assistant secretary for nuclear energy in the U.S. Office of Nuclear Energy. Huff is a professor of nuclear, plasma and radiological engineering in the Grainger College of Engineering at the University of Illinois Urbana-Champaign.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {University of Illinois Urbana-Champaign News Bureau},
	author = {Forrest, Sharita},
	month = may,
	year = {2021},
	file = {Snapshot:/Users/huff/Zotero/storage/FS6PNBHV/1199806555.html:text/html},
}

@misc{huff_nuclear_2023,
	address = {West Lafayette, IN, United States},
	type = {Lecture {Series}: {Understanding} {Tomorrow}'s {Nuclear} {Energy}},
	title = {Nuclear {Power} in 2050 - {Small} {Modular} {Reactor} ({SMR}) {Nuclear} {Study} - {Purdue} {University}},
	url = {https://www.purdue.edu/administrative-operations/nuclear/events/huff-lecture.php},
	abstract = {In this talk, Assistant Secretary Huff will provide a potential vision for the future of nuclear power globally and will describe what the federal government, particularly the Department of Energy{\textquoteright}s Office of Nuclear Energy (DOE NE), is doing today to bring that vision into reality by 2050. This work includes laying the groundwork for peaceful nuclear power to help the U.S. reach net-zero emissions by 2050, for securing and sustaining both the front and back ends of our nuclear fuel cycle and for expanding international nuclear energy cooperation. This talk will highlight the DOE NE mission, vision and programs contributing to these goals as well as the opportunities and challenges ahead. These challenges and opportunities include a need to mobilize bold private capital investments, scale-up a skilled workforce, revive and invent critical supply chains and underpin it all with processes and policies that consider equity and justice.},
	urldate = {2024-05-23},
	author = {Huff, Kathryn},
	month = jan,
	year = {2023},
	note = {https://www.youtube.com/watch?v=5JIcTx70wfA},
	file = {Nuclear Power in 2050 - Small Modular Reactor (SMR) Nuclear Study - Purdue University:/Users/huff/Zotero/storage/HKZ6I782/huff-lecture.html:text/html},
}

@article{weiss_arrow_2022,
	title = {{\textquoteleft}{An} arrow in our quiver:{\textquoteright} 15 minutes with {Dr}. {Kathryn} {Huff}, {Assistant} {Secretary} of {Energy} for {Nuclear} {Energy}},
	volume = {15},
	shorttitle = {{\textquoteleft}{An} arrow in our quiver},
	url = {https://www.exchangemonitor.com/an-arrow-in-our-quiver-15-minutes-with-dr-kathryn-huff-assistant-secretary-of-energy-for-nuclear-energy/},
	abstract = {Assistant Secretary of Energy for Nuclear Energy Kathryn Huff is optimistic about her opportunity to contribute to the federal government{\textquoteright}s 30-year quest},
	language = {en-US},
	number = {22},
	urldate = {2024-05-23},
	journal = {ExchangeMonitor: RadWaste Monitor},
	author = {Weiss, Benjamin},
	collaborator = {Huff, Kathryn},
	month = jun,
	year = {2022},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/XL948L8V/an-arrow-in-our-quiver-15-minutes-with-dr-kathryn-huff-assistant-secretary-of-energy-for-nuclea.html:text/html},
}

@article{dabbs_people_2023,
	title = {People to watch at {DOE}, {Interior}, {FERC}},
	url = {https://www.eenews.net/articles/people-to-watch-at-doe-interior-ferc/},
	abstract = {These officials will play critical roles in determining the direction of clean energy deployment, oil and gas leasing and interstate transmission in 2023.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {E\&E News by POLITICO EnergyWire},
	author = {Dabbs, Brian and Richards, Heather and Willson, Miranda},
	month = feb,
	year = {2023},
	file = {Snapshot:/Users/huff/Zotero/storage/BKS7F5K2/people-to-watch-at-doe-interior-ferc.html:text/html},
}

@misc{huff_state_2023,
	address = {United States Capitol Building},
	type = {Public {Panel}},
	title = {The {State} of {Play} for {Nuclear} {Energy} in the {United} {States} {\textbar} {Briefing} {\textbar} {EESI}},
	url = {https://www.eesi.org/briefings/view/041923nuclear},
	abstract = {The Office of Nuclear Energy (NE) within the Department of Energy (DOE) works to advance nuclear energy science and technology to meet U.S. energy, environmental, and economic needs. NE focuses on research and development (R\&D) that prioritizes the continued operation of the current fleet of nuclear reactors, building new reactors, securing and sustaining the nuclear fuel cycle, and expanding international nuclear cooperation.
The R\&D budget of NE supports nuclear science and technology missions by national laboratories, universities, and industry.
Stopping the premature closure of existing nuclear power plants due to economic reasons can save gigawatts of clean firm power on the grid.
Nuclear energy is the largest source of carbon-free energy in the United States. It accounts for 18 percent of all electricity generated and 47 percent of all carbon emissions-free electricity in the United States.
R\&D programs enhance the performance of nuclear energy plants, extend their lifetime, reduce operating costs, and develop advanced fuels.
Historically, conventional nuclear power plants run at single power, at baseload, and cannot vary their generation. However, advanced nuclear technology provides many opportunities for reactors to vary in power to complement renewable energy facilities. Advanced nuclear technology also provides thermal storage capabilities that allow reactors to stay at high temperatures while the amount of electricity they dispatch to the grid can vary.
Developing small modular reactors (SMRs) and micro-reactors will offer siting flexibility, scalability, and energy uses beyond electricity. With less space required for emergency planning zones, SMRs can be more suitable for environments like repurposed retired and retiring fossil fuel plants.
NE is developing micro-reactors for off-grid communities and backup power, the kind of situations that diesel generators often address.
There are a number of communities and assets across the country that we cannot leave behind in the transition to net-zero carbon emissions by 2050.
Nuclear reactors are especially suited to leveraging grid, workforce, and other assets at retiring or retired coal plant sites.
Repurposing unabated fossil plants could deliver place-based solutions to advance an equitable energy transition.
A recent DOE study shows that 80 percent of U.S. coal communities could benefit from replacing their coal plants with nuclear ones. Each community could gain 650 new permanent jobs, additional economic activity of \$275 million, and an 86 percent reduction in greenhouse gas emissions. Leveraging existing infrastructure would reduce total system costs.
The DOE has recently released reports on long-duration energy storage, clean hydrogen, and commercializing advanced nuclear.
To get to the net-zero carbon emissions by 2050 goal, the buildout of nuclear energy will need to be aggressive. Clean firm power will be necessary to support variable renewable energy.
To secure and sustain the global nuclear fuel cycle, conversion and enrichment capacity must be expanded, a strategy for integrated waste management of spent nuclear fuel must be developed, and consent-based approaches to siting interim storage facilities must be implemented.
A consent-based siting approach would consolidate the 70 locations across the country where communities are currently hosting spent nuclear fuel but never agreed to host it for the long term. The DOE was supposed to take title of this fuel in 1988.
This consent-based approach prioritizes people and communities; seeks willing and informed consent; is flexible, adaptive, and collaborative; is responsive to community concerns; centers equity and environmental justice; and is informed by public feedback.
NE supports R\&D cooperation across borders to ensure research focuses on peaceful uses of nuclear power as well as to ensure the ability of the United States to have a voice in global leadership on this topic.},
	urldate = {2024-05-23},
	author = {Huff, Kathryn},
	month = apr,
	year = {2023},
	file = {The State of Play for Nuclear Energy in the United States | Briefing | EESI:/Users/huff/Zotero/storage/BGZIEG2P/041923nuclear.html:text/html},
}

@misc{justin_h_s_breaux_energy_2022,
	address = {Instagram},
	title = {Energy justice for all: a conversation with {Kathryn} {Huff} from the {Department} of {Energy} {\textbar} {Argonne} {National} {Laboratory}},
	shorttitle = {Energy justice for all},
	url = {https://www.anl.gov/article/energy-justice-for-all-a-conversation-with-kathryn-huff-from-the-department-of-energy},
	abstract = {Under the stands of the University of Chicago's Stagg Field on Dec. 2, 1942, scientists created the world's first self-sustaining nuclear chain reaction. 

80 years later, nuclear energy accounts for 10 percent of the world{\textquoteright}s electricity and is instrumental in new fields of inquiry where researchers use radioactive isotopes to treat disease and understand how the body works.

In this Instagram Live conversation, Kathryn Huff joins Andrew Breshears for a discussion on the role innovation in advanced nuclear reactors will play in creating a  carbon-neutral economy.},
	language = {en},
	urldate = {2024-05-23},
	author = {{Justin H S Breaux}},
	collaborator = {{Kathryn Huff} and {Andrew Breshears}},
	month = jan,
	year = {2022},
	note = {https://www.youtube.com/watch?v=WFs8D8t3xd8},
	file = {Snapshot:/Users/huff/Zotero/storage/QNQJ2MN8/energy-justice-for-all-a-conversation-with-kathryn-huff-from-the-department-of-energy.html:text/html},
}

@article{drelich_federal_2022,
	address = {New London, CT},
	title = {Federal energy officials visit {Waterford} to discuss nuclear storage efforts},
	journal = {The Day},
	author = {Drelich, Kimberly},
	month = dec,
	year = {2022},
	note = {Publication Title: Day, The (New London, CT)},
}

@misc{leila_fadel_what_2022,
	title = {What role does nuclear power play in the {U}.{S}. effort to cut greenhouse gas emissions?},
	url = {https://www.npr.org/2022/11/11/1135984019/what-role-does-nuclear-power-play-in-the-u-s-effort-to-cut-greenhouse-gas-emissi},
	abstract = {NPR's Leila Fadel speaks with Kathryn Huff, an official at the Department of Energy, about the future of nuclear energy in the United States.},
	language = {en},
	urldate = {2024-05-23},
	journal = {Morning Edition (NPR)},
	publisher = {NPR},
	author = {{Leila Fadel}},
	month = nov,
	year = {2022},
	note = {Publisher: National Public Radio, Inc},
	file = {Audio:/Users/huff/Zotero/storage/AI74TI2E/N et al. - 2022 - What role does nuclear power play in the U.S. effo.mp3:audio/mpeg;Transcript:/Users/huff/Zotero/storage/FTR9CRV3/1135984019.html:text/html},
}

@article{curtis_maines_2021,
	address = {Bangor, Maine},
	title = {Maine's nuclear waste could find a home if communities volunteer to take it},
	url = {http://www.bangordailynews.com/2021/11/30/news/midcoast/maines-nuclear-waste-could-find-a-home-if-communities-volunteer-to-take-it/},
	abstract = {Although it's the federal government{\textquoteright}s obligation to create a permanent facility for waste disposal, nuclear facilities across the country have been left to find solutions for temporary storage.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {Bangor Daily News},
	author = {Curtis, Abigail},
	month = nov,
	year = {2021},
	note = {Publication Title: Bangor Daily News (ME)},
	file = {Snapshot:/Users/huff/Zotero/storage/XSD26KJZ/maines-nuclear-waste-could-find-a-home-if-communities-volunteer-to-take-it.html:text/html},
}

@misc{exchangemonitor_biden_2022,
	type = {News {Blog}},
	title = {Biden admin sends {NE}-1 nom {Huff} to {Senate}},
	url = {https://www.exchangemonitor.com/biden-admin-sends-ne-1-nom-huff-to-senate/},
	abstract = {The White House on Monday officially nominated Kathryn Huff to lead the Department of Energy{\textquoteright}s Office of Nuclear Energy, sending her nomination to the},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {ExchangeMonitor Morning Briefing},
	author = {{ExchangeMonitor}},
	month = feb,
	year = {2022},
	file = {Snapshot:/Users/huff/Zotero/storage/9URMH8QL/biden-admin-sends-ne-1-nom-huff-to-senate.html:text/html},
}

@article{huff_investing_2022,
	title = {Investing in {America}'s {Nuclear} {Future}},
	volume = {145},
	issn = {00256501},
	url = {https://proxy2.library.illinois.edu/login?url=https://search.ebscohost.com/login.aspx?direct=true&db=asn&AN=160498218&site=ehost-live&scope=site},
	abstract = {The article focuses on the Inflation Reduction Act (IRA) and the Bipartisan Infrastructure Law (BIL) by the administration of U.S. President Joe Biden. Topics discussed include nuclear energy considered as source of the carbon-free electricity in the U.S., clean energy production tax credits included in the IRA, and terawatt transformation through the clean energy transition.},
	number = {1},
	urldate = {2024-05-23},
	journal = {Mechanical Engineering},
	author = {Huff, Kathryn},
	month = jan,
	year = {2022},
	note = {Publisher: American Society of Mechanical Engineers},
	keywords = {AMERICA, CLEAN energy, FAST reactors, FUEL cycle, NUCLEAR energy, NUCLEAR fission, NUCLEAR power plants, NUCLEAR reactors},
	pages = {16--16},
	file = {EBSCO Full Text:/Users/huff/Zotero/storage/JPVGK8AV/Huff - 2022 - Investing in America's Nuclear Future.pdf:application/pdf},
}

@article{abrams_does_2024,
	title = {Does the {S} {Still} {Stand} for {Small}?},
	volume = {146},
	issn = {0025-6501},
	url = {https://doi.org/10.1115/1.2024-Jan4},
	doi = {10.1115/1.2024-Jan4},
	abstract = {Small modular reactors (SMRs), designed to be faster to build and easier to site, have long been touted as a replacement for conventional reactors. SMRs{\textemdash}the International Atomic Energy Agency classifies the technology as reactors generating less than 300 MW of electricity{\textemdash}are conceived as a means to make nuclear power simpler and less challenging to add to the grid. But questions remain as to just what size is optimal for SMRs.},
	number = {1},
	urldate = {2024-05-23},
	journal = {Mechanical Engineering},
	author = {Abrams, Michael},
	month = jan,
	year = {2024},
	pages = {30--35},
	file = {Full Text PDF:/Users/huff/Zotero/storage/IABXV8RU/Abrams - 2024 - Does the S Still Stand for Small.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/PVD4PHU9/Does-the-S-Still-Stand-for-Small-As-Small-Modular.html:text/html},
}

@article{mahoney_us_2022,
	address = {Hartford, CT},
	chapter = {Connecticut News},
	edition = {Daily e-Edition},
	title = {U.{S}. nuclear chief details plans to find disposal site for spent {CT} nuclear waste},
	url = {https://www.courant.com/2022/12/20/us-nuclear-energy-chief-details-plans-to-find-storage-sites-for-spent-ct-nuclear-waste/},
	urldate = {2024-05-23},
	journal = {Hartford Courant},
	author = {Mahoney, Edmund H.},
	month = dec,
	year = {2022},
	file = {U.S. nuclear chief details plans to find disposal site for spent CT nuclear waste:/Users/huff/Zotero/storage/MIJWQVDN/us-nuclear-energy-chief-details-plans-to-find-storage-sites-for-spent-ct-nuclear-waste.html:text/html},
}

@misc{honney_finland_2023,
	title = {Finland and {US} increase nuclear co-operation},
	url = {https://www.neimagazine.com/news/finland-and-us-increase-nuclear-co-operation-10842419/},
	abstract = {Finland{\textquoteright}s Ministry of Economic Affairs \& Employment and the US Department of Energy (DOE) have signed a memorandum of understanding (MOU) on nuclear energy and nuclear waste management. {\textquotedblleft}Its purpose is to intensify cooperation between administrations, companies and research institutes in Finland and the US concerning the peaceful use of nuclear power,{\textquotedblright} the Finnish Ministry said. The MOU was signed by the Ministry{\textquoteright}s Director General, Riku Huttunen, and Dr Kathryn Huff, Assistant Secretary at the DOE{\textquoteright}s Office of Nuclear Energy.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {Nuclear Engineering International},
	author = {Honney, Tracey},
	month = may,
	year = {2023},
	file = {Snapshot:/Users/huff/Zotero/storage/PNNTJL6X/finland-and-us-increase-nuclear-co-operation-10842419.html:text/html},
}

@misc{romania_acting_2021,
	type = {Government},
	title = {Acting {Assistant} {Secretary} for {Nuclear} {Energy} {Huff}{\textquoteright}s {Trip} to {Romania}},
	url = {https://ro.usembassy.gov/acting-assistant-secretary-for-nuclear-energy-huffs-trip-to-romania/},
	abstract = {On July 30, 2021, Acting Assistant Secretary for Nuclear Energy at the U.S. Department of Energy, Dr. Kathryn Huff and Charg{\'e} d{\textquoteright}affaires David Muniz},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {U.S. Embassy in Romania},
	author = {Romania, U. S. Mission},
	month = jul,
	year = {2021},
	note = {media},
	file = {Snapshot:/Users/huff/Zotero/storage/DPV5V5TC/acting-assistant-secretary-for-nuclear-energy-huffs-trip-to-romania.html:text/html},
}

@misc{huff_teller_2022,
	address = {Aiken, SC},
	type = {Named {Lecture}},
	title = {Teller {Lecture} and {Banquet} {Citizens} for {Nuclear} {Technology} {AwarenessCNTA}-{TO}-{HOST}-{ANNUAL}-{EDWARD}-{TELLER}-{LECTURE}-{ON}-{NOVEMBER}-1.pdf},
	url = {https://cntaware.org/wp-content/uploads/2022/09/CNTA-TO-HOST-ANNUAL-EDWARD-TELLER-LECTURE-ON-NOVEMBER-1.pdf},
	abstract = {The Annual Edward Teller Lecture and Banquet (also referred to as the Teller Lecture) is an event hosted by Citizens for Nuclear Technology Awareness with the goal to reach out to its members and the public.
The event includes a reception, dinner, and lecturer. Distinguished guest speaker is the Honorable Kathryn Huff, Assistant Secretary for Nuclear Energy. There are many awards to be given out at the annual event including the Robert Maher Memorial Scholarship, the Distinguished Scientist Award, and the Nuclear Service Award.},
	urldate = {2024-05-23},
	author = {Huff, Kathryn},
	month = nov,
	year = {2022},
	file = {CNTA-TO-HOST-ANNUAL-EDWARD-TELLER-LECTURE-ON-NOVEMBER-1.pdf:/Users/huff/Zotero/storage/WNEQXLUC/CNTA-TO-HOST-ANNUAL-EDWARD-TELLER-LECTURE-ON-NOVEMBER-1.pdf:application/pdf},
}

@misc{huff_energy_2022,
	title = {Energy {Blog}: {Investing} in {America}{\textquoteright}s {Nuclear} {Future} - {ASME}},
	shorttitle = {Energy {Blog}},
	url = {https://www.asme.org/topics-resources/content/energy-blog-investing-in-americas-nuclear-future},
	abstract = {Recent legislation allocates money toward replacing fossil-fueled power plants with advanced nuclear reactors.},
	language = {en},
	urldate = {2024-05-23},
	journal = {American Society of Mechanical Engineers Energy Blog},
	author = {Huff, Kathryn},
	month = dec,
	year = {2022},
	file = {Snapshot:/Users/huff/Zotero/storage/4NKZ3Y32/energy-blog-investing-in-americas-nuclear-future.html:text/html},
}

@article{moore_biden_2024,
	title = {Biden {Official} {Presses} {Congress} for {Uranium} {Enrichment} {Funding}},
	volume = {Environment and Energy},
	url = {https://news.bloomberglaw.com/environment-and-energy/biden-official-presses-congress-for-uranium-enrichment-funding},
	urldate = {2024-05-23},
	journal = {Bloomberg Law},
	author = {Moore, Daniel},
	month = jan,
	year = {2024},
	file = {Biden Official Presses Congress for Uranium Enrichment Funding:/Users/huff/Zotero/storage/EFBBS73I/XE4A1078000000.html:text/html},
}

@misc{brown_federal_2024,
	title = {Federal money could supercharge state efforts to preserve nuclear power},
	url = {https://stateline.org/2024/02/12/federal-money-could-supercharge-state-efforts-to-preserve-nuclear-power/},
	abstract = {A \$1.5 billion federal loan could enable a privately owned Michigan nuclear plant to be the first to restart operations after shutting down.},
	language = {en-US},
	urldate = {2024-05-23},
	journal = {Stateline Energy and Environment},
	author = {Brown, Alex},
	month = feb,
	year = {2024},
	file = {Snapshot:/Users/huff/Zotero/storage/TWI8R5RN/federal-money-could-supercharge-state-efforts-to-preserve-nuclear-power.html:text/html},
}

@misc{huff_demonstration_2021,
	type = {U.{S}. {Department} of {Energy} {Press} {Release}},
	title = {Demonstration {AND} {Test} {Reactors}: {Both} {Are} {Necessary} for {Innovation}},
	shorttitle = {Demonstration {AND} {Test} {Reactors}},
	url = {https://www.energy.gov/ne/articles/demonstration-and-test-reactors-both-are-necessary-innovation},
	abstract = {DOE's Dr. Kathryn Huff breaks down the importance of demonstrating new reactor technologies and expanding the Department's R\&D infrastructure.},
	language = {en},
	urldate = {2024-05-29},
	journal = {Energy.gov},
	author = {Huff, Kathryn D.},
	month = jul,
	year = {2021},
	note = {https://youtu.be/5mB\_ZCX5TcE},
	file = {Snapshot:/Users/huff/Zotero/storage/Y4BISH75/demonstration-and-test-reactors-both-are-necessary-innovation.html:text/html},
}

@article{boyle_energy_2021,
	address = {Monticello, UT},
	chapter = {News},
	edition = {September 21, 2021},
	title = {Energy {Fuels} has big plans for {White} {Mesa} {Mill}},
	url = {https://sjrnews.com/news/energy-fuels-has-big-plans-white-mesa-mill},
	abstract = {Energy Fuels Inc. announced the creation of a new foundation, along with highlighting new strategies for their company moving forward, at a two-day open house last week.},
	language = {en},
	urldate = {2024-05-29},
	journal = {San Juan Record},
	author = {Boyle, David},
	month = sep,
	year = {2021},
	file = {Snapshot:/Users/huff/Zotero/storage/C3T3BWM3/energy-fuels-has-big-plans-white-mesa-mill.html:text/html},
}

@misc{la_follette_school_of_public_affairs_insightful_2021,
	type = {University {News}},
	title = {Insightful discussions abound at {Climate} {Policy} {Forum}},
	url = {https://lafollette.wisc.edu/news/insightful-discussions-abound-at-climate-policy-forum/},
	abstract = {Nearly 300 policymakers, practitioners, community leaders, and researchers attended the second annual La Follette Forum on October 6 in Madison.},
	language = {en-US},
	urldate = {2024-05-29},
	journal = {La Follette School of Public Affairs},
	author = {{La Follette School of Public Affairs}},
	month = oct,
	year = {2021},
	file = {Snapshot:/Users/huff/Zotero/storage/F2DTPNAN/insightful-discussions-abound-at-climate-policy-forum.html:text/html},
}

@misc{smith_introducing_2017-1,
	type = {presentation},
	title = {Introducing {JOSS}: {The} {Journal} of {Open} {Source} {Software}},
	shorttitle = {Introducing {JOSS}},
	url = {https://figshare.com/articles/presentation/Introducing_JOSS_The_Journal_of_Open_Source_Software/5208151/1},
	abstract = {Talk presented at the 2017 Python in Science Conference (SciPy), on 13 July 2017 in Austin, TX.AbstractThis talk describes the motivation and progress of the Journal of Open Source Software (JOSS), a free, open-access journal designed to publish brief articles about research software. The primary purpose of JOSS is to enable developers of research software to receive citation credit equivalent to typical archival publications. Rather than a review of a lengthy software paper (including, e.g., methodology, validation, sample results), JOSS submissions undergo rigorous peer review of both the abstract and software itself, including documentation, tests, continuous integration, and licensing. The JOSS review process is modeled on the established approach of the rOpenSci collaboration. The entire submission and review process occurs openly on GitHub; articles not yet accepted remain visible and under review until the authors make appropriate changes for acceptance{\textemdash}unlike other journals, articles requiring major revision are not rejected. JOSS published 111 articles in its first year (May 2016{\textendash}2016), with {\textgreater}50 articles under review.},
	language = {en},
	urldate = {2024-06-01},
	author = {Smith, Arfon and Barba, Lorena A. and Githinji, George and Gymrek, Melissa and Huff, Kathryn and Katz, Daniel S. and Madan, Christopher and Mayes, Abigail Cabunoc and Moerman, Kevin M. and Niemeyer, Kyle and Prins, Pjotr and Ram, Karthik and Rokem, Ariel and Teal, Tracy and Valls Guimera, Roman and Vanderplas, Jacob T.},
	month = jul,
	year = {2017},
	doi = {10.6084/m9.figshare.5208151.v1},
	note = {Publisher: figshare},
	file = {Full Text PDF:/Users/huff/Zotero/storage/5K3IAXAV/Smith et al. - 2017 - Introducing JOSS The Journal of Open Source Softw.pdf:application/pdf},
}

@article{munk_review_2019,
	title = {Review of {Hybrid} {Methods} for {Deep}-{Penetration} {Neutron} {Transport}},
	volume = {193},
	issn = {0029-5639, 1943-748X},
	url = {https://www.tandfonline.com/doi/full/10.1080/00295639.2019.1586273},
	doi = {10.1080/00295639.2019.1586273},
	abstract = {Methods for deep-penetration radiation transport remain important for radiation shielding, nonproliferation, nuclear threat reduction, and medical applications. As these applications become more ubiquitous, the need for accurate and reliable transport methods appropriate for these systems persists. For such systems, hybrid methods often obtain reliable answers in the shortest time by leveraging the speed and uniform uncertainty distribution of a deterministic solution to bias Monte Carlo transport and reduce the variance in the solution. This work reviews the state of the art among such hybrid methods. First, we summarize variance reduction (VR) for Monte Carlo radiation transport and existing efforts to automate these techniques. Relations among VR, importance, and the adjoint solution of the neutron transport equation are then discussed. Based on this exposition, the work transitions from theory to a critical review of existing VR implementations in modern nuclear engineering software. At present, the Consistent AdjointDriven Importance Sampling (CADIS) and Forward-Weighted Consistent Adjoint-Driven Importance Sampling (FW-CADIS) hybrid methods are the gold standard by which to reduce the variance in problems that have deeply penetrating radiation. The CADIS and FW-CADIS methods use an adjoint scalar flux to generate VR parameters for Monte Carlo radiation transport. Additionally, efforts to incorporate angular information into VR methods for Monte Carlo are summarized. Finally, we assess various implementations of these methods and the degree to which they improve VR for their target applications.},
	language = {en},
	number = {10},
	urldate = {2024-06-01},
	journal = {Nuclear Science and Engineering},
	author = {Munk, Madicken and Slaybaugh, Rachel N.},
	month = oct,
	year = {2019},
	pages = {1055--1089},
	file = {Munk and Slaybaugh - 2019 - Review of Hybrid Methods for Deep-Penetration Neut.pdf:/Users/huff/Zotero/storage/F6A2CC7H/Munk and Slaybaugh - 2019 - Review of Hybrid Methods for Deep-Penetration Neut.pdf:application/pdf},
}

@article{allen_fluoride-salt-cooled_nodate,
	title = {Fluoride-{Salt}-{Cooled}, {High}-{Temperature} {Reactor} ({FHR}) {Development} {Roadmap} and {Test} {Reactor} {Performance} {Requirements} {White} {Paper}},
	language = {en},
	author = {Allen, Todd and Anderson, Mark and Anness, Michael and Blandford, Edward and Chapin, Douglas and Chen, Kun and Dai, Zhimin and Flanagan, George and Forget, Benoit and Forsberg, Charles and Greenspan, Ehud and Holcomb, David and Hu, Lin-Wen and Kelly, John and Kohse, Gordon and Carpenter, David and Richard, Joshua and Romatoski, Becky and Stempien, John Dennis and Cao, Guoping and Zheng, Guiqiu and Andreades, Charalampos and Cisneros, Anselmo and Huddar, Lakshana and Laufer, Michael and Krumwiede, David and Munk, Madicken and Scarlat, Raluca and Seifried, Jeffrey and Zweibaum, Nicolas},
	file = {Allen et al. - Fluoride-Salt-Cooled, High-Temperature Reactor (FH.pdf:/Users/huff/Zotero/storage/2EVUC56V/Allen et al. - Fluoride-Salt-Cooled, High-Temperature Reactor (FH.pdf:application/pdf},
}

@misc{kong_scalable_2019,
	title = {A scalable multilevel domain decomposition preconditioner with a subspace-based coarsening algorithm for the neutron transport calculations},
	url = {http://arxiv.org/abs/1906.07743},
	doi = {10.48550/arXiv.1906.07743},
	abstract = {The multigroup neutron transport equations has been widely used to study the interactions of neutrons with their background materials in nuclear reactors. High-resolution simulations of the multigroup neutron transport equations using modern supercomputers require the development of scalable parallel solving techniques. In this paper, we study a scalable transport method for solving the algebraic system arising from the discretization of the multigroup neutron transport equations. The proposed transport method consists of a fully coupled Newton solver for the generalized eigenvalue problems and GMRES together with a novel multilevel domain decomposition preconditioner for the Jacobian system. The multilevel preconditioner has been successfully used for many problems, but the construction of coarse spaces for certain problems, especially for unstructured mesh problems, is expensive and often unscalable. We introduce a new subspace-based coarsening algorithm to address this issue by exploring the structure of the matrix in the discretized version of the neutron transport problems. We numerically demonstrate that the proposed transport method is highly scalable with more than 10,000 processor cores for the 3D C5G7 benchmark problem on unstructured meshes with billions of unknowns. Compared with the traditional multilevel domain decomposition method, the new approach equipped with the subspace-based coarsening algorithm is much faster on the construction of coarse spaces.},
	urldate = {2024-06-04},
	publisher = {arXiv},
	author = {Kong, Fande and Wang, Yaqi and Gaston, Derek R. and Lindsay, Alexander D. and Permann, Cody J. and Martineau, Richard C.},
	month = jun,
	year = {2019},
	note = {arXiv:1906.07743 [cs, math]},
	keywords = {Computer Science - Distributed, Parallel, and Cluster Computing, Mathematics - Numerical Analysis},
	annote = {Comment: Submitted to Numerical Linear Algebra with Applications (Copper Mountain Conference special issue). 23 pages and 11 figures},
	file = {arXiv Fulltext PDF:/Users/huff/Zotero/storage/W9P7FA7Z/Kong et al. - 2019 - A scalable multilevel domain decomposition precond.pdf:application/pdf;arXiv.org Snapshot:/Users/huff/Zotero/storage/QYFBQJ9D/1906.html:text/html},
}

@techreport{schwen_summary_2020,
	title = {Summary of {Bison} documentation and {UX} milestones - {NEAMS} {FY20} {Report}},
	url = {https://www.osti.gov/biblio/1734544},
	abstract = {This summary report contains an overview of work performed under the work package entitled {\textquotedblleft}MS- 20IN020107 - BISON advanced numerical model development and usability improvements - INL{\textquotedblright}, which is focused on the development and support of the fuel performance code BISON [1]. The second chapter lists FY20 milestones titles, completion schedule, and milestone level. Subsequent chapters summarize and demonstrate completion of milestones and activities. The last chapter outlines FY21 proposed future work.},
	language = {English},
	number = {INL/EXT-20-59954-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Schwen, Daniel and Yushu, Dewen and Pitts, Stephanie A. and Vanwasshenova, Daniel J. and Martin Recuero, Antonio and McDowell, Dylan James and Lindsay, Alexander D. and Spencer, Benjamin W.},
	month = oct,
	year = {2020},
	doi = {10.2172/1734544},
	file = {Full Text PDF:/Users/huff/Zotero/storage/2VFV3J6W/Schwen et al. - 2020 - Summary of Bison documentation and UX milestones -.pdf:application/pdf},
}

@techreport{seifert_material_nodate,
	title = {Material {Flows} and {On}-line {Reprocessing} in {Serpent}},
	abstract = {The stochastic transport and depletion code Serpent2 allows the capability of feeding and removing materials during depletion. This is a necessary feature for molten salt reactor modeling, but it lacks sufficient documentation and is limited by the static depletion volumes. This paper provides documentation for this on-line reprocessing functionality by presenting the mathematics and constraints behind the various material flow control settings as well as the respective flow rate functions. Multiple solutions for working around the static volume limitation are discussed, specifically through an overflow bucket or repeated restarts of the software with updates of the volumetric data provided.},
	language = {en},
	author = {Seifert, Luke and Wheeler, Alexander and Chv{\'a}la, Ondrej},
	file = {Seifert et al. - Material Flows and On-line Reprocessing in Serpent.pdf:/Users/huff/Zotero/storage/49DSMBIZ/Seifert et al. - Material Flows and On-line Reprocessing in Serpent.pdf:application/pdf},
}

@techreport{lindsay_user-oriented_2022,
	title = {User-oriented {Improvements} in the {MOOSE} {Framework} in {Support} of {Multiphysics} {Simulation}},
	url = {https://www.osti.gov/biblio/1995774},
	abstract = {The Multiphysics Object-Oriented Simulation Environment (MOOSE) framework is a foundational capability used by the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program to create over 15 different simulation tools for advanced nuclear reactors. Due to this ubiquity, improvements to the framework in support of modeling and simulation goals are critical to the program. These improvements can take many forms, including optimization, improved user experience, streamlined application programming interfaces (APIs), parallelism, and new capabilities. The work transcribed in this report was conducted in direct support of the simulation tools and has already been deployed or will be deployed in the coming months. The capabilities were implemented in the same order as they are covered in this report: chainable execution objects or executors, support for transfers between same-level applications in a coupling scheme, support for boundary/subdomain restricted transfers, support for transfers between applications with different coordinate or unit systems, support for MOOSE applications in the NEAMS Workbench, deployment of the MOOSE application of the Idaho National Laboratory (INL) high-performance computing (HPC) OnDemand platform, the addition of a triangular meshing library in libMesh, and increased support of face variables.},
	language = {English},
	number = {INL/RPT-22-67144-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Lindsay, Alexander D. and Harbour, Logan H. and Giudicelli, Guillaume Louis and Icenhour, Casey T. and Kong, Fande and Stogner, Roy Hulen and Langley, Brandon and Delchini, Marco and Lefebvre, Robert and Gaston, Derek R. and Permann, Cody J.},
	month = may,
	year = {2022},
	doi = {10.2172/1995774},
	file = {Full Text PDF:/Users/huff/Zotero/storage/9I95QSJS/Lindsay et al. - 2022 - User-oriented Improvements in the MOOSE Framework .pdf:application/pdf},
}

@article{dechant_verification_2023,
	title = {Verification and validation of the open-source plasma fluid code: {Zapdos}},
	volume = {291},
	issn = {0010-4655},
	shorttitle = {Verification and validation of the open-source plasma fluid code},
	url = {https://www.sciencedirect.com/science/article/pii/S0010465523001820},
	doi = {10.1016/j.cpc.2023.108837},
	abstract = {Zapdos is an open-source finite element plasma fluid solver based on the MOOSE multiphysics framework. This paper outlines Zapdos verification, benchmarking, and validation efforts for 1D and 2D RF capacitively-coupled plasma discharge models for mid-range pressures (0.1 - 1 Torr). The verification process involved using the method of manufactured solutions to assess Zapdos spatial and temporal error convergence. L2 errors ranged from 10-2 to 10-4, while the convergence's slope were in agreement with the predicted slopes for the tested variable and time integration orders. The benchmarking process involved comparisons to previously results from the validated finite element code, LSODI [1], [2], [3]. These works included 1D and 2D simulations for a range of plasma parameters (densities, temperatures, voltage, etc.). For the 1D cases, Zapdos and LSODI results were in very good agreement. In the 2D cases, variable behaviors matched, with slight discrepancies in peak values. The validation process involved comparisons to experimental works including electron density measurements by microwave interferometry [4] and metastable density measurements by planar laser-induced fluorescence imaging [5]. Results shown reasonable agreement at higher pressure, with results starting to diverge at low pressures. Probable causes for this diverges are the limitation of the fluid assumption for plasmas at low pressure, or the need for more robust boundary conditions. Overall, Zapdos shown reasonable results for the verification, benchmarking, and validation efforts, and Zapdos can be downloaded at https://github.com/shannon-lab/zapdos.
Program summary
Program Title: Zapdos CPC Library link to program files: https://doi.org/10.17632/j76jr9m66p.1 Developer's repository link: https://github.com/shannon-lab/zapdos Licensing provisions: LGPL-2.1 Programming language: C++, Python Supplementary material: shannon-lab.github.io/zapdos Nature of problem: For the plasma computational community, multiphysics packages are needed for the highly couple physics seen in plasma problems (e.g. chemistry, fluid flow, heat transfer, electromagnetic, etc.). One limiting factor for these types of computational research is the high cost to purchase the licenses needed for established multiphysics packages, such as COMSOL. An additional problem that can arise is the limited ability to add new physics to these existing frameworks, in such a way that new physics can be easily coupled to current models. For any new software that wants to tackle these problems, the question of verification and validation for these codes needs to be addressed. Solution method: Zapdos is an open-source finite element plasma fluid solver based on the MOOSE multiphysics framework. MOOSE (Multiphysics Object Oriented Simulation Environment) solves highly nonlinear, tightly coupled sets of partial differential equations (PDEs) and houses multiple physics applications that can be easily coupled together. Zapdos, along with the MOOSE ecosystem, is all free, open-source, and completing customizable with no black box components. Zapdos has gone through verification and validation for applications common in the plasma computational community. Additional comments including restrictions and unusual features: Zapdos, along with MOOSE and other MOOSE applications, require an Unix based operating system.},
	urldate = {2024-06-04},
	journal = {Computer Physics Communications},
	author = {DeChant, Corey and Icenhour, Casey and Keniley, Shane and Gall, Grayson and Lindsay, Alexander and Curreli, Davide and Shannon, Steven},
	month = oct,
	year = {2023},
	keywords = {Finite element method, Fluid approximation, Method of manufactured solutions, Open-source, Plasma, Verification and validation},
	pages = {108837},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/P2CK2GEH/S0010465523001820.html:text/html},
}

@article{icenhour_moose_2024,
	title = {The {MOOSE} electromagnetics module},
	volume = {25},
	issn = {2352-7110},
	url = {https://www.sciencedirect.com/science/article/pii/S2352711023003175},
	doi = {10.1016/j.softx.2023.101621},
	abstract = {The Multiphysics Object-Oriented Simulation Environment (MOOSE) electromagnetics module has been developed to increase MOOSE physics module capabilities, enabling standalone and coupled computational electromagnetics within the MOOSE multiphysics ecosystem. The module is actively being utilized in the areas of plasma physics and advanced manufacturing, and it currently provides initial demonstrated capability in multi-dimensional, complex-valued electromagnetic wave propagation, electrostatic contact, reflection and transmission, and electromagnetic eigenvalue problems. Two-dimensional wave propagation and one-dimensional wave reflection and transmission are showcased as examples in this work. The modularity, parallelism, and plug-in infrastructure for custom future development is inherited from MOOSE itself, and the module can be used with both MOOSE-based and external codes, giving great flexibility.},
	urldate = {2024-06-04},
	journal = {SoftwareX},
	author = {Icenhour, Casey T. and Lindsay, Alexander D. and Permann, Cody J. and Martineau, Richard C. and Green, David L. and Shannon, Steven C.},
	month = feb,
	year = {2024},
	keywords = {Electromagnetics, MOOSE, Multiphysics, Simulation},
	pages = {101621},
}

@techreport{lindsay_improvement_2021,
	title = {Improvement of {Numerical} {Methods} in {Pronghorn}},
	url = {https://www.osti.gov/biblio/2008350},
	abstract = {During the fiscal year of 2021, the finite-volume method (FVM) was deployed in Pronghorn to provide improved efficiency, stability, and accuracy for coarse-mesh, thermal-hydraulics problems. While the main goals of fiscal year 2021 were met, several issues emerged from the early deployment of the finite-volume method in Pronghorn. These issues were: The compressible and incompressible formulations that were implemented are inadequate for many nuclear reactor flow problems; Omission of terms accounting for the porosity and Darcy-Forchheimer body force discontinuities in the Rhie-Chow interpolation lead to oscillations in pressure and velocity at these discontinuities; The FVM lacks a correction for non-orthogonal grids for computing accurate pressure gradient leading to loss of accuracy in regions with skewed elements; The FVM currently uses a monolithic solver. Monolithic solvers have issues dealing with the saddle-point nature of the discretized fluid equations. The result are bad convergence if direct factorization is not used and large memory consumption when direct factorization is used. These four issues are addressed in this report. In particular, we report the completion of the following task: Implementation of a weakly compressible formulation in the MOOSE Navier-Stokes module; Implementation of Moukalled{\textquoteright}s method for including body forces in the RCI. Additionally, we identified the need to smooth the porosity using Moukalled{\textquoteright}s face-cell smoothing operator; Implementation of a non-orthogonal correction for the Green-Gauss gradient computation; Preliminary implementation of a SIMPLE segregated solver.},
	language = {English},
	number = {INL/EXT-21-65482},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Lindsay, Alexander D. and Tano Retamales, Mauricio Eduardo and Giudicelli, Guillaume Louis and German, Peter and Schunert, Sebastian},
	month = dec,
	year = {2021},
	doi = {10.2172/2008350},
	file = {Full Text PDF:/Users/huff/Zotero/storage/3EXHK7M4/Lindsay et al. - 2021 - Improvement of Numerical Methods in Pronghorn.pdf:application/pdf},
}

@article{dechant_verification_2023-1,
	title = {Verification methods for drift{\textendash}diffusion reaction models for plasma simulations},
	volume = {32},
	issn = {0963-0252, 1361-6595},
	url = {https://iopscience.iop.org/article/10.1088/1361-6595/acce65},
	doi = {10.1088/1361-6595/acce65},
	abstract = {Compared to other computational physics areas such as codes for general computational fluid dynamics, the documentation of verification methods for plasma fluid codes remains under developed. Current analytical solutions for plasma are often highly limited in terms of testing highly coupled physics, due to the harsh assumptions needed to derive even simple plasma equations. This work highlights these limitations, suggesting the method of manufactured solutions (MMSs) as a potential option for future verification efforts. To demonstrate the flexibility of MMS in verifying these highly coupled systems, the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework was utilized. Thanks to the MOOSE framework{\textquoteright}s robustness and modularity, as well as to its physics module capabilities and ecosystem applications (i.e. Zapdos and the chemical reaction network) developed for plasma physics modeling and simulation, this report lays the groundwork for a structured method of conducting plasma fluid code verification.},
	language = {en},
	number = {4},
	urldate = {2024-06-04},
	journal = {Plasma Sources Science and Technology},
	author = {DeChant, Corey and Icenhour, Casey and Keniley, Shane and Lindsay, Alexander and Gall, Grayson and Clein Hizon, Kimberly and Curreli, Davide and Shannon, Steven},
	month = apr,
	year = {2023},
	pages = {044006},
	file = {DeChant et al. - 2023 - Verification methods for drift{\textendash}diffusion reaction .pdf:/Users/huff/Zotero/storage/4SU4TWXN/DeChant et al. - 2023 - Verification methods for drift{\textendash}diffusion reaction .pdf:application/pdf},
}

@article{lindsay_verification_nodate,
	title = {Verification methods for drift{\textendash}diffusion reaction models for plasma simulations - {IOPscience}},
	volume = {32},
	url = {https://iopscience.iop.org/article/10.1088/1361-6595/acce65/meta},
	abstract = {Compared to other computational physics areas such as codes for general computational fluid dynamics, the documentation of verification methods for plasma fluid codes remains under developed. Current analytical solutions for plasma are often highly limited in terms of testing highly coupled physics, due to the harsh assumptions needed to derive even simple plasma equations. This work highlights these limitations, suggesting the method of manufactured solutions (MMSs) as a potential option for future verification efforts. To demonstrate the flexibility of MMS in verifying these highly coupled systems, the Multiphysics Object-Oriented Simulation Environment (MOOSE) framework was utilized. Thanks to the MOOSE framework's robustness and modularity, as well as to its physics module capabilities and ecosystem applications (i.e. Zapdos and the chemical reaction network) developed for plasma physics modeling and simulation, this report lays the groundwork for a structured method of conducting plasma fluid code verification.},
	number = {4},
	urldate = {2024-06-04},
	journal = {IOP Science home Accessibility Help Plasma Sources Science and Technology},
	author = {Lindsay, Alexander and DeChant, Corey and Icenhour, Casey and Keniley, Shane and Gall, Grayson and Hizon, Kimberly Clein and Curreli, Davide and Shannon, Steven},
	file = {Verification methods for drift{\textendash}diffusion reaction models for plasma simulations - IOPscience:/Users/huff/Zotero/storage/B2DUYSBP/meta.html:text/html},
}

@article{recuero_practical_2023,
	title = {On {Practical} {Aspects} of {Variational} {Consistency} in {Contact} {Dynamics}},
	volume = {18},
	issn = {1555-1415},
	url = {https://doi.org/10.1115/1.4056589},
	doi = {10.1115/1.4056589},
	abstract = {Usage of contact mechanics methodologies is a pervasive modeling requirement in dynamic simulations. While for some trivial problems, solutions taken from analytical geometry are available, use of a finite element framework is common to achieve formulation generality. This work explores two dynamic contact formulations: one based on the traditional node-to-segment (NTS) approach, and a variationally consistent segment-to-segment (STS) mortar formulation. The NTS formulation employed here enforces the constraints kinematically (i.e., the interpenetration is enforced to the solver tolerance), whereas the mortar approach uses Lagrange multipliers to enforce the contact constraints. Both approaches are implemented in the open-source finite element framework Multiphysics Object-Oriented Simulation Environment (MOOSE). The results highlight two relevant contact-interface-related dynamic phenomena in finite element simulations. First, stabilization of contact constraints is discussed, taking into account the evolution of the total energy in a benchmark problem. Second, the influence of finite element discretization on both of the aforementioned contact formulations is analyzed by exercising a large-deformation example with continuous relative sliding. Variationally consistent contact approaches such as the mortar formulation lead to improved energy preservation and avoid spurious excitation of the system's frequencies. This is especially relevant in settings where inertia and vibrations are of importance.},
	number = {081003},
	urldate = {2024-06-04},
	journal = {Journal of Computational and Nonlinear Dynamics},
	author = {Recuero, Antonio and Lindsay, Alexander},
	month = may,
	year = {2023},
	file = {Full Text PDF:/Users/huff/Zotero/storage/3CFRHM6A/Recuero and Lindsay - 2023 - On Practical Aspects of Variational Consistency in.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/YH7TY9RP/On-Practical-Aspects-of-Variational-Consistency-in.html:text/html},
}

@article{giudicelli_30_2024,
	title = {3.0 - {MOOSE}: {Enabling} massively parallel multiphysics simulations},
	volume = {26},
	issn = {2352-7110},
	shorttitle = {3.0 - {MOOSE}},
	url = {https://www.sciencedirect.com/science/article/pii/S235271102400061X},
	doi = {10.1016/j.softx.2024.101690},
	abstract = {The development of MOOSE has kept accelerating since the last release, with over 2,100 pull requests merged over the last 30 months that involved nearly fifty contributors across close to a dozen institutions internationally. The growth in MOOSE's capabilities and downstream applications is reflected in the growth of the community. User support provided on the GitHub discussions forum has steadily increased to nearly 50 daily interactions. New simulation projects, notably to model advanced nuclear reactor and fusion devices, are driving a significant expansion of the capabilities. This paper reports on these developments, with several major released features, new physics modules, and key improvements to the user experience and simulation workflow.},
	urldate = {2024-06-04},
	journal = {SoftwareX},
	author = {Giudicelli, Guillaume and Lindsay, Alexander and Harbour, Logan and Icenhour, Casey and Li, Mengnan and Hansel, Joshua E. and German, Peter and Behne, Patrick and Marin, Oana and Stogner, Roy H. and Miller, Jason M. and Schwen, Daniel and Wang, Yaqi and Munday, Lynn and Schunert, Sebastian and Spencer, Benjamin W. and Yushu, Dewen and Recuero, Antonio and Prince, Zachary M. and Nezdyur, Max and Hu, Tianchen and Miao, Yinbin and Jung, Yeon Sang and Matthews, Christopher and Novak, April and Langley, Brandon and Truster, Timothy and Nobre, Nuno and Alger, Brian and Andrs, David and Kong, Fande and Carlsen, Robert and Slaughter, Andrew E. and Peterson, John W. and Gaston, Derek and Permann, Cody},
	month = may,
	year = {2024},
	keywords = {Finite-element, Finite-volume, Framework, Multiphysics, Multiscale, Parallel},
	pages = {101690},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/LYW48F89/S235271102400061X.html:text/html},
}

@patent{shannon_very_2016,
	title = {Very high frequency ({VHF}) driven atmospheric plasma sources and point of use fertigation of irrigation water utilizing plasma production of nitrogen bearing species},
	url = {https://patents.google.com/patent/US9475710B2/en},
	nationality = {US},
	language = {en},
	assignee = {North Carolina State University},
	number = {US9475710B2},
	urldate = {2024-06-04},
	author = {Shannon, Steven C. and Knappe, Detlef and Byrns, Brandon and Wooten, Daniel and Lindsay, Alexander},
	month = oct,
	year = {2016},
	keywords = {cylindrical tube, outer cylindrical, plasma, source, water},
	file = {Full Text PDF:/Users/huff/Zotero/storage/KUTG5KH9/Shannon et al. - 2016 - Very high frequency (VHF) driven atmospheric plasm.pdf:application/pdf},
}

@techreport{yushu_m3_2021,
	title = {M3 milestone: {Advanced} contact 2021},
	shorttitle = {M3 milestone},
	url = {https://www.osti.gov/biblio/1836106},
	abstract = {This report describes advanced contact approaches and implementations in FY21 for use in emerging reactors with geometries that differ from LWR/EBR-II cylindrical fuel. Contact remains a challenging and crucially important component of our modeling toolkit. While significant improvements have been made through mortar and automatic differentiation, we explored advanced approaches (i.e., dual mortar) that yields better conditioned systems and will improve the robustness and performance of BISON contact problems. This effort is relevant to emerging reactor types, such as micro reactors and the corresponding complex and numerous contact surfaces. In this report, improvements of the mortar-based contact formulation are described. Benchmark problems and BISON assessment cases are included to demonstrate the improvements and advantages that are brought by the recent capability. Remaining issues are discussed and corresponding development plans are outlined.},
	language = {English},
	number = {INL/EXT-21-62750-Rev001},
	urldate = {2024-06-04},
	institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Yushu, Dewen and Martin Recuero, Antonio and Schwen, Daniel and Lindsay, Alexander D. and Spencer, Benjamin W.},
	month = sep,
	year = {2021},
	file = {Full Text PDF:/Users/huff/Zotero/storage/L7NEY4DP/Yushu et al. - 2021 - M3 milestone Advanced contact 2021.pdf:application/pdf},
}

@article{lindsay_moose_2023,
	title = {{MOOSE} {Navier}{\textendash}{Stokes} module},
	volume = {23},
	issn = {2352-7110},
	url = {https://www.sciencedirect.com/science/article/pii/S2352711023001991},
	doi = {10.1016/j.softx.2023.101503},
	abstract = {The MOOSE Navier{\textendash}Stokes module solves mass, momentum, energy, and passive scalar conservation equations in the context of fluid flow. The module supports solution of these equations in both free flow and porous medium contexts and for a range of fluid compressibility. The conservation equations can be discretized in space using continuous Galerkin finite elements or with cell centered finite volumes.},
	urldate = {2024-06-04},
	journal = {SoftwareX},
	author = {Lindsay, Alexander and Giudicelli, Guillaume and German, Peter and Peterson, John and Wang, Yaqi and Freile, Ramiro and Andrs, David and Balestra, Paolo and Tano, Mauricio and Hu, Rui and Zou, Ling and Gaston, Derek and Permann, Cody and Schunert, Sebastian},
	month = jul,
	year = {2023},
	keywords = {Finite elements, Finite volumes, Navier{\textendash}Stokes, Porous medium},
	pages = {101503},
	file = {Full Text:/Users/huff/Zotero/storage/8BLSPQ2F/Lindsay et al. - 2023 - MOOSE Navier{\textendash}Stokes module.pdf:application/pdf;ScienceDirect Snapshot:/Users/huff/Zotero/storage/2TCQDES5/S2352711023001991.html:text/html},
}

@inproceedings{icenhour_multi-physics_2018,
	address = {Oregon Convention Center, Portland, OR},
	title = {Multi-physics {Object} {Oriented} {Simulation} {Environment} ({MOOSE})},
	url = {https://www.osti.gov/biblio/1498270},
	abstract = {This two-day workshop is a hands-on introduction to the Multi-Physics Object Oriented Simulation Environment (MOOSE). MOOSE is a simulation framework built from PETSc that enables efficient simulation of complex physical systems with minimal programming background. Attendees are encouraged to visit the MOOSE website at www.mooseframework.org and walk through the step by step process of installing the framework on their computer. Support through this process is provided through the MOOSE Google Group message board. The workshop itself will consist of interactive modules where instructors from the MOOSE development team will work with attendees to build a simple plasma model. Each module will build on previous modules to introduce fundamental MOOSE features that will combine to demonstrate simulation capabilities for low temperature plasma modeling. The intention is not to provide an exhaustive overview of simulation capabilities but to instead provide attendees with the necessary tools to build unique simulation capabilities for their specific research challenges. Users should attend the workshop with laptop computers with MOOSE installed to allow for interactive instruction. At the completion of the workshop attendees will be able to install and run MOOSE and associated applications as well as carry out plasma simulations studies.},
	language = {English},
	urldate = {2024-06-04},
	publisher = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Icenhour, Casey and Keniley, Shane and DeChant, Corey and Permann, Cody and Lindsay, Alex and Martineau, Richard and Curreli, Davide and Shannon, Steven},
	month = nov,
	year = {2018},
	note = {Report Number: INL/CON-18-51061-Rev000},
	file = {Full Text PDF:/Users/huff/Zotero/storage/IBBTLHFJ/Icenhour et al. - 2018 - Multi-physics Object Oriented Simulation Environme.pdf:application/pdf},
}

@techreport{novascone_summary_2019,
	title = {Summary of {Bison} milestones and activities - {NEAMS} {FY2019} {Report}},
	url = {https://www.osti.gov/biblio/1768049},
	abstract = {This summary report contains an overview of work performed under the work package entitled {\textquotedblleft}FY2019 NEAMS Engineering Scale Fuel Performance{\textquotedblright}, which is focused on the development and support of the fuel performance code Bison [1]. The second chapter lists FY19 milestones titles, completion schedule, and milestone level. Subsequent chapters summarize and demonstrate completion of milestones and activities. The last chapter outlines FY20 proposed future work.},
	language = {English},
	number = {INL/EXT-19-55699-Rev. 01},
	urldate = {2024-06-04},
	institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States); Argonne National Lab. (ANL), Argonne, IL (United States); Los Alamos National Lab. (LANL), Los Alamos, NM (United States); Southwestern Scientific, Mission Viejo, CA (United States)},
	author = {Novascone, Stephen R. and Casagranda, Albert and Aagesen, Jr and Beeler, B. W. and Jiang, Wen and Jokisaari, Andrea M. and McDowell, Dylan James and Lindsay, Alexander D. and Tompkins, James B. and Pastore, Giovanni and Zabriskie, Adam X. and Schwen, Daniel and Williamson, Richard L. and Spencer, Benjamin W. and Slaughter, Andrew E. and Miao, Yinbin and Oaks, Aaron and Yacout, Abdellatif M. and Matthews, C. and Stafford, Shane},
	month = sep,
	year = {2019},
	doi = {10.2172/1768049},
	file = {Full Text PDF:/Users/huff/Zotero/storage/78JSBTTV/Novascone et al. - 2019 - Summary of Bison milestones and activities - NEAMS.pdf:application/pdf},
}

@article{simon_tritium_2022,
	title = {Tritium {Transport} {Modeling} at the {Pore} {Scale} in {Ceramic} {Breeder} {Materials} {Using} {TMAP8}},
	volume = {50},
	issn = {1939-9375},
	url = {https://ieeexplore.ieee.org/abstract/document/9831077},
	doi = {10.1109/TPS.2022.3183525},
	abstract = {Fusion reactors depend on the blanket material to breed and release tritium at the same rate or faster than it is consumed by the fusion reaction. Cellular ceramic breeders (CCBs) are dense materials that can maintain a high tritium breeding ratio while promoting tritium release because of highly connected pores. Assessing the tritium breeding capabilities of these materials requires a combination of extensive experimental and modeling efforts. In this work, we develop and calibrate a multiphysics model of tritium transport. This novel model accounts for ceramic and pore diffusion, trapping and detrapping, and several surface reactions at the pore surface. We perform a sensitivity analysis and calibrate the model by comparing its predictions against experimental measurements of deuterium absorption. The calibrated model is then used to model tritium absorption in samples with different pore microstructures to investigate the effect of pore interconnectivity on tritium absorption. The model is part of the development of the multiscale, multiphysics framework for tritium transport [i.e., the Tritium Migration Analysis Program (TMAP8)], which is itself built on top of the finite-element multiphysics framework multiphysics object-oriented simulation environment (MOOSE). This study demonstrates some of TMAP8{\textquoteright}s capabilities and is the first step toward assessing the tritium breeding capabilities of ceramic breeder material designs.},
	number = {11},
	urldate = {2024-06-04},
	journal = {IEEE Transactions on Plasma Science},
	author = {Simon, Pierre-Cl{\'e}ment A. and Humrickhouse, Paul W. and Lindsay, Alexander D.},
	month = nov,
	year = {2022},
	note = {Conference Name: IEEE Transactions on Plasma Science},
	keywords = {Absorption, Cellular ceramic breeder (CCB) materials, Ceramics, Computational modeling, Data models, Deuterium, fusion technology, mechanistic modeling, mesoscale simulation, Object oriented modeling, Predictive models, tritium breeding ratio, tritium population},
	pages = {4465--4471},
	file = {IEEE Xplore Abstract Record:/Users/huff/Zotero/storage/YRADDABR/9831077.html:text/html;IEEE Xplore Full Text PDF:/Users/huff/Zotero/storage/FZYY9FCB/Simon et al. - 2022 - Tritium Transport Modeling at the Pore Scale in Ce.pdf:application/pdf},
}

@techreport{schunert_improvements_2022,
	title = {Improvements in {High} {Temperature} {Gas} {Cooled} {Reactor} {Modeling} {Capabilities} in the {Pronghorn} {Code}},
	url = {https://www.osti.gov/biblio/1998243},
	abstract = {This report details the improvement of pebble bed reactor modeling capabilities in the Pronghorn code in fiscal year 2022. The following accomplishments are reported: Deployment of weakly compressible finite volume formulation to the HTR- PM reference plan model; Enable modeling of stagnant gas gaps in the finite volume formulation; Enable using all Pronghorn correlations available in the finite element version in the finite volume version; Modeling of decay heat in pebble bed reactors; Simplifying the input for multiphysics equilibrium core calculations and significant reduction of execution time; Implementation of advanced correlations developed by the Center of Excellence for Thermal-Fluids Applications in Nuclear Energy. In addition, this report includes a development plan for Pronghorn and associated NEAMS tools for prismatic gas-cooled reactors.},
	language = {English},
	number = {INL/RPT-22-69263-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Schunert, Sebastian and Mohammad Jaradat, Mustafa Kamel and Calvin, Olin W. and Giudicelli, Guillaume Louis and Lindsay, Alexander D. and Wang, Yaqi and Tano Retamales, Mauricio Eduardo and Walker, Samuel Austin},
	month = sep,
	year = {2022},
	doi = {10.2172/1998243},
	file = {Full Text PDF:/Users/huff/Zotero/storage/L5AEZ6WU/Schunert et al. - 2022 - Improvements in High Temperature Gas Cooled Reacto.pdf:application/pdf},
}

@article{weiss_characterization_2022,
	title = {Characterization of the {Finite} {Element} {Computational} {Fluid} {Dynamics} {Capabilities} in the {Multiphysics} {Object} {Oriented} {Simulation} {Environment}},
	volume = {9},
	issn = {2332-8983},
	url = {https://doi.org/10.1115/1.4054685},
	doi = {10.1115/1.4054685},
	abstract = {The multiphysics object-oriented simulation environment (moose) is a code package that couples a variety of physics modules, allowing for highly accessible multiphysics simulations. The physics modules include a finite element Navier{\textendash}Stokes (N{\textendash}S) module that is designed to solve laminar fluid dynamics problems. The usage of this module in multiple recent studies coupled with the growing interest in moose for usage in nonlight water reactor safety studies by the Nuclear Regulatory Commission (NRC) prompted the authors to investigate the computational fluid dynamics capabilities of moose. A two-dimensional laminar flow past a circular cylinder scenario is simulated in the moose framework to investigate the effectiveness of the N{\textendash}S module. Simulations assumed an unsteady laminar flow with a Reynolds number of 200. To verify the results from moose, similar simulations were conducted using the well-utilized simulation of turbulent flow in arbitrary regions{\textemdash}computational continuum mechanics C++ (star-ccm+) finite volume code. Results from both codes are also compared to some results from literature. Velocity and pressure profiles of both transient simulations were compared. The numerical and input errors in moose are also visualized with contour plots to qualitatively understand the evolution of the errors across time and space. The comparisons between moose and star-ccm+ showed nearly perfect agreement between the codes for velocity and pressure, especially after the development of the vortex street in later time-steps. The force coefficients showed excellent agreement after the development of the vortex street, but demonstrated notable discrepancies prior to the vortex street development, which is likely due to how each code simulated the approach to the vortex street in earlier time-steps.},
	number = {021402},
	urldate = {2024-06-04},
	journal = {Journal of Nuclear Engineering and Radiation Science},
	author = {Weiss, Abdullah G. and Zaidan, Laith J. and Bani Ahmad, Mohammad T. H. and Abdoelatef, M. Gomaa and Peterson, John W. and Lindsay, Alexander D. and Kong, Fande and Ahmed, Karim and Kimber, Mark L.},
	month = jun,
	year = {2022},
	file = {Full Text PDF:/Users/huff/Zotero/storage/85BTYK36/Weiss et al. - 2022 - Characterization of the Finite Element Computation.pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/LF8LA7RT/Characterization-of-the-Finite-Element.html:text/html},
}

@techreport{spencer_bison_2018,
	title = {Bison {Improvements} for {Robustness} and {Speed}},
	url = {https://www.osti.gov/biblio/1467562},
	abstract = {Early in its development, the primary emphasis of efforts to improve the Bison fuel performance code were focused on initial development of new capabilities. As Bison has matured and become adopted by a wider set of users, it has become clear that a number of robustness issues needed to be addressed to ensure that the code can reliably produce a converged solution. This need became particularly evident when a recent effort by Westinghouse Electric Company to simulate all of the fuel rods in a reactor using Bison resulted in approximately 30\% of the models failing to run to completion because of lack of convergence or other errors that were encountered. It is important to emphasize that there was no evidence that Bison generated results that were incorrect for the set of models exercised. In many cases, issues such as those encountered could be addressed by adjusting solver-related parameters. However, there is no question that for Bison to become widely adopted for production work, it needs to be inherently far more robust than it was. Because of this, a concerted effort was undertaken to improve Bison's robustness, or its ability to reliably obtain converged solutions under a wider variety of conditions. As a result of this work, a number of high-priority areas for improvement for modeling light water reactor (LWR) fuel rods have been identified and addressed. As a result of this work, the number of failing Bison analyses in the aforementioned set of simulations for a full core has been reduced to a fraction of a percent. In addition, the robustness of Bison models using the VERA core simulator has been significantly improved. This is important because all of the Bison models representing individual fuel rods must run to completion successfully for the full core model to run to completion. This report provides summaries of the identified sources of robustness issues in Bison and the development that was done to resolve these issues. It also summarizes the addition of new capabilities to address deficiencies in Bison's ability to include needed aspects of LWR fuel behavior, and improvements that were made to improve Bison's solution efficiency.},
	language = {English},
	number = {INL/EXT-18-45704-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Spencer, Benjamin W. and Williamson, Richard L. and Lindsay, Alexander D. and Kong, Fande and Gardner, Russell J. and Hales, Jason D. and Casagranda, Albert and Schwen, Daniel and Chen, Hailong and Prakash, Naveen and Matthews, Christopher and Unal, Cetin},
	month = jun,
	year = {2018},
	doi = {10.2172/1467562},
	file = {Full Text PDF:/Users/huff/Zotero/storage/QH3DY5RP/Spencer et al. - 2018 - Bison Improvements for Robustness and Speed.pdf:application/pdf},
}

@misc{rykhlevskii_online_2019,
	title = {Online {Reprocessing} {Simulation} for {Thorium}-{Fueled} {Molten} {Salt} {Breeder} {Reactor}},
	url = {https://engrxiv.org/preprint/view/388},
	doi = {10.31224/osf.io/38gaq},
	language = {en},
	urldate = {2024-06-04},
	publisher = {Engineering Archive},
	author = {Rykhlevskii, Andrei and Lindsay, Alexander and Huff, Kathryn},
	month = jan,
	year = {2019},
	keywords = {molten salt, online reprocessing},
	file = {Full Text PDF:/Users/huff/Zotero/storage/5S4W8247/Rykhlevskii et al. - 2019 - Online Reprocessing Simulation for Thorium-Fueled .pdf:application/pdf},
}

@article{kong_highly_2020,
	title = {A {Highly} {Parallel} {Multilevel} {Newton}--{Krylov}--{Schwarz} {Method} with {Subspace}-{Based} {Coarsening} and {Partition}-{Based} {Balancing} for the {Multigroup} {Neutron} {Transport} {Equation} on {Three}-{Dimensional} {Unstructured} {Meshes}},
	volume = {42},
	issn = {1064-8275},
	url = {https://epubs.siam.org/doi/abs/10.1137/19M1249060},
	doi = {10.1137/19M1249060},
	abstract = {The multigroup neutron transport equation is crucial for studying the motion of neutrons and their interaction with materials. Numerical simulation of the multigroup neutron transport equation is computationally challenging because the equation is defined on a high-dimensional phase space, the computational spatial domain is complex, and the materials are heterogeneous. A scalable parallel solver is required to address such a challenge. In this paper, we study a highly parallel Newton--Krylov--Schwarz (NKS) method consisting of a Newton-based eigenvalue solver, a Krylov subspace method, and a novel multilevel Schwarz preconditioner. The multilevel method is one of the most popular preconditioners for accelerating neutron transport calculations, but the construction of coarse spaces can be expensive and often unscalable when a large number of processors is used. We propose a novel matrix coarsening algorithm in which a multilevel hierarchy is constructed using a single-component matrix instead of the full matrix of the neutron transport equation. This new coarsening algorithm is referred to as {\textquotedblleft}subspace-based coarsening.{\textquotedblright} Above 8,000 processors, we show a 13x enhancement in multilevel preconditioner setup time when using the subspace-based coarsening method. A partition-based balancing strategy is studied to enhance the parallel efficiency of the NKS algorithm by equalizing the work for each processor. A hierarchical mesh partitioning algorithm is employed to generate a large number of submeshes while minimizing off-node communication. We demonstrate that the proposed algorithm is scalable with more than 10,000 processors for a realistic application on three-dimensional unstructured meshes with a few billion degrees of freedom. Neutron transport calculations using the improved NKS algorithm are twice as fast as those based on the unmodified NKS solver when over 8,000 processors are employed.},
	number = {5},
	urldate = {2024-06-04},
	journal = {SIAM Journal on Scientific Computing},
	author = {Kong, Fande and Wang, Yaqi and Gaston, Derek R. and Permann, Cody J. and Slaughter, Andrew E. and Lindsay, Alexander D. and DeHart, Mark D. and Martineau, Richard C.},
	month = jan,
	year = {2020},
	note = {Publisher: Society for Industrial and Applied Mathematics},
	pages = {C193--C220},
	file = {Full Text PDF:/Users/huff/Zotero/storage/HCWXPCR7/Kong et al. - 2020 - A Highly Parallel Multilevel Newton--Krylov--Schwa.pdf:application/pdf},
}

@article{dhulipala_development_2022,
	title = {Development, verification, and validation of comprehensive acoustic fluid-structure interaction capabilities in an open-source computational platform},
	volume = {51},
	copyright = {{\textcopyright} 2022 John Wiley \& Sons Ltd. This article has been contributed to by U.S. Government employees and their work is in the public domain in the USA.},
	issn = {1096-9845},
	url = {https://onlinelibrary.wiley.com/doi/abs/10.1002/eqe.3659},
	doi = {10.1002/eqe.3659},
	abstract = {The acoustic fluid-structure interaction (FSI) formulation is a practical numerical approach for the seismic analysis of fluid-filled tanks. However, there are no verification and validation studies reported in the literature that demonstrate the ability of an acoustic FSI numerical model to predict responses important to structural and mechanical design for intense translational and rotational earthquake inputs. Herein, an acoustic FSI formulation is implemented in the open-source Multiphysics Object-Oriented Simulation Environment (MOOSE), and is formally verified and validated using analytical solutions and code-to-code verification, and experimental data, respectively. The analytical solutions are for small amplitude, unidirectional seismic inputs. The code-to-code verification utilizes a previously verified and validated Arbitrary Lagrangian-Eulerian (ALE) numerical model in the commercial finite element code LS-DYNA. The validation studies utilize a comprehensive data set assembled from results of 3D earthquake-simulator tests of a fluid-filled vessel. The acoustic numerical model in MOOSE is verified and validated for hydrodynamic pressures and support reactions except for cases that involve significant convective response. For small amplitude inputs, numerically predicted wave heights match those of the analytical solutions. The numerical model is not verified and validated for wave height calculations under intense 3D seismic inputs. The run times for the acoustic FSI simulations in MOOSE are an order of magnitude, or more, shorter than for the corresponding ALE simulations in LS-DYNA. The utility of the MOOSE acoustic FSI implementation is demonstrated by seismic analysis of a building equipped with a fluid-filled, advanced nuclear reactor.},
	language = {en},
	number = {10},
	urldate = {2024-06-04},
	journal = {Earthquake Engineering \& Structural Dynamics},
	author = {Dhulipala, Somayajulu L. N. and Bolisetti, Chandrakanth and Munday, Lynn B. and Hoffman, William M. and Yu, Ching-Ching and Mir, Faizan Ul Haq and Kong, Fande and Lindsay, Alexander D. and Whittaker, Andrew S.},
	year = {2022},
	note = {\_eprint: https://onlinelibrary.wiley.com/doi/pdf/10.1002/eqe.3659},
	keywords = {advanced nuclear reactors, experimental validation, fluid-structure interaction, multiphysics simulations, numerical model verification, seismic analysis},
	pages = {2188--2219},
	file = {Snapshot:/Users/huff/Zotero/storage/F6INJFUL/eqe.html:text/html},
}

@techreport{lindsay_neams-multiphysics_2021,
	title = {{NEAMS}-{Multiphysics} {Technical} {Assistance} in {FY21}},
	url = {https://www.osti.gov/biblio/1847109},
	abstract = {The Multiphysics Object Oriented Simulation Environment (MOOSE) [1] is a massively parallel finite-element/volume package for multiphysics simulation in science and engineering. The package focuses on providing rapid-development capabilities for engineering applications by leveraging well-built features from libMesh [2] and the Portable Extensible Toolkit for Scientific Computation (PETSc) [3]. Fiscal year 2021 (FY-21) was the first year with funding dedicated to supporting MOOSE-derived applications relevant to the Nuclear Engineering Advanced Modeling and Simulation (NEAMS) program. In this report we outline the work done to support NEAMS applications such as BISON, Griffin, Pronghorn, and System Analysis Module (SAM).},
	language = {English},
	number = {INL/EXT-21-64493-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Lindsay, Alexander D. and Kong, Fande and Giudicelli, Guillaume Louis and Carlsen, Robert W. and Stogner, Roy Hulen and Slaughter, Andrew E.},
	month = aug,
	year = {2021},
	doi = {10.2172/1847109},
	file = {Submitted Version:/Users/huff/Zotero/storage/P6IFS3XD/Lindsay et al. - 2021 - NEAMS-Multiphysics Technical Assistance in FY21.pdf:application/pdf},
}

@techreport{schunert_deployment_2021,
	title = {Deployment of the {Finite} {Volume} {Method} in {Pronghorn} for {Gas} and {Salt} cooled {Pebble} {Bed} {Reactors}},
	url = {https://www.osti.gov/biblio/2008349},
	abstract = {This report summarizes the activities related to {\textquotedblright}Complete FHR and HTGR pebble bed simulator, including initial validation{\textquotedblright} funded by the NEAMS thermal-hydraulics focus area. The activity revolves around the coarse-mesh thermal-hydraulics code Pronghorn and its application to gas and salt cooled Pebble bed reactor (PBR). The main difference between gas and salt cooled PBR from a thermal-hydraulics perspective is the fluid. To address the difference in fluid behavior, two separate approaches are implemented in the MOOSE Navier Stokes module: 1) a Boussinesq approximation and 2) a fully compressible formulation. The developed finite volume method capabilities are used for improving pre-existing gas-cooled and salt-cooled pebble-bed reactor models. A steady-state, multiphysics gas-cooled pebble-bed reactor model is created that couples the equilibrium core depletion capability developed in previous work, and the finite volume method capability developed for this report. The salt-cooled pebble-bed reactor model is upgraded to use the incompressible finite volume method capability and then extended to three spatial dimensions. Finally, several verification-and-validation exercises performed with Pronghorn are documented using the verification-and-validation report of the MooseDoc system. The goal of this effort to document the verification-and-validation level of Pronghorn and improve stakeholder confidence in the results obtained with Pronghorn.},
	language = {English},
	number = {INL/EXT-21-63189},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Schunert, Sebastian and Giudicelli, Guillaume Louis and Lindsay, Alexander D. and Balestra, Paolo and Harper, Sterling and Freile, Ramiro and Tano, Mauricio and Ragusa, Jean},
	month = jun,
	year = {2021},
	doi = {10.2172/2008349},
	file = {Submitted Version:/Users/huff/Zotero/storage/FTDUEX98/Schunert et al. - 2021 - Deployment of the Finite Volume Method in Pronghor.pdf:application/pdf},
}

@techreport{giudicelli_neams_2021,
	title = {{NEAMS} {TH} {CRAB}},
	url = {https://www.osti.gov/biblio/1847108},
	abstract = {The MOOSE framework is a library designed to make it straightforward for physicists and engineers to model partial differential equations using finite element and finite volume methods. Finite elements have been a part of the framework library since MOOSE's inception over a decade ago. Initial finite volume capability, however, was added only as recently as May of 2020. Since that time, significant work has been conducted to develop fluid modeling capability based on the finite volume method. Much of this work has taken place in MOOSE's navier\_stokes module and in the NEAMS program's coarse mesh CFD code Pronghorn. We report here on development in MOOSE and Pronghorn of incompressible, porous incompressible, and weakly compressible finite volume simulation capabilities and their application to modeling of MSR and FHR advanced reactor concepts.},
	language = {English},
	number = {INL/EXT-21-64625-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Giudicelli, Guillaume Louis and Lindsay, Alexander D. and Freile, Ramiro and Lee, Jieun},
	month = sep,
	year = {2021},
	doi = {10.2172/1847108},
	file = {Full Text PDF:/Users/huff/Zotero/storage/ZIF5X8HX/Giudicelli et al. - 2021 - NEAMS TH CRAB.pdf:application/pdf},
}

@article{recuero_mortar_2022,
	title = {A mortar thermomechanical contact computational framework for nuclear fuel performance simulation},
	volume = {394},
	issn = {0029-5493},
	url = {https://www.sciencedirect.com/science/article/pii/S0029549322001625},
	doi = {10.1016/j.nucengdes.2022.111808},
	abstract = {Nuclear fuel performance simulations involve the modeling of complex physical phenomena, ranging from fission gas release to fuel swelling and other temperature-induced effects. For light-water reactors (LWRs), swelling of the fuel and the pressure it imposes on the clad when they come into contact causes permanent clad deformation. Accurately characterizing the fuel-cladding interaction, which involves multiple physics, is essential to accurately simulate the fuel/cladding system. Thermomechanical modeling of this problem using a variationally consistent enforcement (e.g., a mortar approach) has been shown to improve the quality of results and facilitate convergence. Here, we present a general multiphysics computational framework for solving nuclear fuel problems using a mortar approach in BISON, a nuclear fuel performance code. Analyses show that using the mortar approach, which enables variationally consistent constraint enforcement, improves the quality of results as compared to the more commonly used node-on-face enforcement for representative LWR nuclear fuel simulations.},
	urldate = {2024-06-04},
	journal = {Nuclear Engineering and Design},
	author = {Recuero, Antonio and Lindsay, Alexander and Yushu, Dewen and Peterson, John W. and Spencer, Benjamin},
	month = aug,
	year = {2022},
	keywords = {Mortar finite element method, Nuclear fuel performance, Simulation, Thermomechanical contact},
	pages = {111808},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/NR3GGL6U/S0029549322001625.html:text/html},
}

@inproceedings{giudicelli_coupled_2021,
	title = {{COUPLED} {MULTIPHYSICS} {MULTISCALE} {TRANSIENT} {SIMULATIONS} {OF} {THE} {Mk1}-{FHR} {REACTOR} {USING} {FINITE} {VOLUME} {CAPABILITIES} {OF} {THE} {MOOSE} {FRAMEWORK}: 2021 {International} {Conference} on {Mathematics} and {Computational} {Methods} {Applied} to {Nuclear} {Science} and {Engineering}, {M} and {C} 2021},
	isbn = {978-1-71388-631-0},
	url = {http://www.scopus.com/inward/record.url?scp=85144600575&partnerID=8YFLogxK},
	doi = {10.13182/M&C21-33948},
	abstract = {Multiphysics simulations are key to reactor safety analysis, especially for novel reactor designs lacking experimental data. Simulation tools within the MOOSE framework, such as the Griffin reactor physics application and the coarse mesh computational fluid dynamics solver Pronghorn, can be coupled to perform such multiphysics transient simulations. We feature those capabilities in tightly-coupled multiphysics transient simulations of a simplified Mk1 PB-FHR reactor. A porous media model based on the incompressible Navier Stokes equation was implemented using the finite volume method for this work. This leverages the newly implemented finite volume discretization feature in MOOSE. Copyright {\textcopyright} 2021 AMERICAN NUCLEAR SOCIETY, INCORPORATED, LA GRANGE PARK, ILLINOIS 60526.All rights reserved.},
	language = {English},
	booktitle = {Proceedings of the {International} {Conference} on {Mathematics} and {Computational} {Methods} {Applied} to {Nuclear} {Science} and {Engineering}, {M} and {C} 2021},
	author = {Giudicelli, G. and Lindsay, A. and Balestra, P. and Carlsen, R. and Ortensi, J. and Gaston, D. and DeHart, M. and Abou-Jaoude, A. and Novak, A.J.},
	year = {2021},
	keywords = {finite volume, Griffin, MOOSE, MSR, multiphysics, PB-FHR, porous media flow, Pronghorn},
	pages = {2251--2262},
	annote = {Cited By :9},
	annote = {Publisher Copyright:Copyright {\textcopyright} 2021 AMERICAN NUCLEAR SOCIETY, INCORPORATED, LA GRANGE PARK, ILLINOIS 60526.All rights reserved.},
	file = {Snapshot:/Users/huff/Zotero/storage/QQBUGPC8/display.html:text/html},
}

@article{abou-jaoude_workflow_2021,
	title = {A workflow leveraging {MOOSE} transient multiphysics simulations to evaluate the impact of thermophysical property uncertainties on molten-salt reactors},
	volume = {163},
	issn = {0306-4549},
	url = {https://www.sciencedirect.com/science/article/pii/S0306454921004229},
	doi = {10.1016/j.anucene.2021.108546},
	abstract = {A new approach is proposed to evaluate the safety of molten-salt reactors (MSRs), using advanced modeling and simulation (M\&S) tools. This approach augments the Monitoring and Inspection (M\&I) concept for fuel qualification by enabling computation of the change in critical safety parameters as a result of altered thermo-physical fuel properties. This work uses newly developed capabilities in the MOOSE framework to perform the requisite M\&S. The neutronics code Griffin, using its neutron diffusion solver, is coupled to the coarse-mesh, multi-dimensional, thermal-hydraulic capabilities of Pronghorn. The resulting new capability enables efficient transient multiphysics simulations of open-pool-type MSR concepts, including delayed neutron precursor advection and beyond design basis events. The proposed approach uses the coupled Griffin/Pronghorn models to perform a sensitivity analysis by perturbing the salt thermophysical properties and evaluating the resulting impact on key safety parameters during an unprotected loss-of-forced-flow accident. In light of the challenges associated with predicting the effect of reactor operations and burnup on bulk salt properties, this work demonstrates how Griffin/Pronghorn multiphysics simulations may be used to evaluate whether changes in salt properties could potentially lead to unsafe reactor configurations.},
	urldate = {2024-06-04},
	journal = {Annals of Nuclear Energy},
	author = {Abou-Jaoude, A. and Harper, S. and Giudicelli, G. and Balestra, P. and Schunert, S. and Martin, N. and Lindsay, A. and Tano, M. and Freile, R.},
	month = dec,
	year = {2021},
	keywords = {Griffin, Molten salt reactors, MOOSE, Multiphysics, Pronghorn, Thermophysical properties, Transients},
	pages = {108546},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/6RM2RM6Q/S0306454921004229.html:text/html},
}

@article{martineau_multiphysics_2020,
	title = {Multiphysics for nuclear energy applications using a cohesive computational framework},
	volume = {367},
	issn = {0029-5493 , 1872-759X},
	url = {https://i-share-uiu.primo.exlibrisgroup.com},
	doi = {10.1016/j.nucengdes.2020.110751},
	abstract = {Multiphysics for nuclear energy applications using a cohesive computational framework-article},
	language = {en},
	urldate = {2024-06-04},
	journal = {Nuclear engineering and design},
	author = {Martineau, R and Andrs, D and Carlsen, R. and Gaston, D. and Hansel, J. and Kong, F. and Lindsay, A. and Permann, C. and Slaughter, A. and Merzari, E. and Hu, Rui and Slaybaugh, R.},
	year = {2020},
	file = {Snapshot:/Users/huff/Zotero/storage/P7T2C7AU/openurl.html:text/html},
}

@article{byrns_vhf_2012,
	title = {A {VHF} driven coaxial atmospheric air plasma: electrical and optical characterization - {IOPscience}},
	volume = {45},
	url = {https://iopscience.iop.org/article/10.1088/0022-3727/45/19/195204/meta},
	doi = {10.1088/0022-3727/45/19/195204},
	abstract = {A coaxially driven VHF plasma source for atmospheric air plasmas has been built and characterized. Electrical and optical characterization of this source present a unique operating regime when compared to state of the art atmospheric systems such as dielectric barrier discharge, pulsed dc, microwave, or ac blown arc discharges. The discharge does not appear to produce streamers or arcs, but instead remains as a steady-state glow located at the end of the inner coaxial power feed. Plasma impedance was determined by comparing the loaded and unloaded impedance of the coaxial source RF input; this termination impedance was combined with a simple high-frequency global model to estimate an electron density of approximately 1011 cm-3 at 400 W delivered power in air. Optical emission characterization of the source shows a monotonic increase in emission with respect with power; the relative intensity of the peaks from excited species, however, remains constant over a power range from 300 to 600 W. This unique source geometry presents a possible pathway for high gas throughput, large area, high power density processes such as surface modification, air purification, media removal and chemical surface treatment.},
	number = {19},
	urldate = {2024-06-04},
	journal = {Journal of Physics D: Applied Physics},
	author = {Byrns, Brandon and Wooten, Daniel and Lindsay, Alexander and Shannon, Steven},
	month = apr,
	year = {2012},
	file = {A VHF driven coaxial atmospheric air plasma\: electrical and optical characterization - IOPscience:/Users/huff/Zotero/storage/79LM7ATA/meta.html:text/html;Full Text:/Users/huff/Zotero/storage/UYPRSARK/A VHF driven coaxial atmospheric air plasma elect.pdf:application/pdf},
}

@article{wmanner_spin-forbidden_2012,
	title = {Spin-forbidden hydrogen atom transfer reactions in a cobalt biimidazoline system},
	volume = {3},
	url = {https://pubs.rsc.org/en/content/articlelanding/2012/sc/c1sc00387a},
	doi = {10.1039/C1SC00387A},
	language = {en},
	number = {1},
	urldate = {2024-06-04},
	journal = {Chemical Science},
	author = {W.~Manner, Virginia and D.~Lindsay, Alex and A.~Mader, Elizabeth and N.~Harvey, Jeremy and M.~Mayer, James},
	year = {2012},
	note = {Publisher: Royal Society of Chemistry},
	pages = {230--243},
	file = {Full Text PDF:/Users/huff/Zotero/storage/YW2QJI5V/W.~Manner et al. - 2012 - Spin-forbidden hydrogen atom transfer reactions in.pdf:application/pdf},
}

@article{lindsay_fully_2016,
	title = {Fully coupled simulation of the plasma liquid interface and interfacial coefficient effects - {IOPscience}},
	volume = {49},
	url = {https://iopscience.iop.org/article/10.1088/0022-3727/49/23/235204/meta},
	doi = {10.1088/0022-3727/49/23/235204},
	abstract = {There is a growing interest in the study of coupled plasma-liquid systems because of their applications to biomedicine, biological and chemical disinfection, agriculture, and other areas. Optimizing these applications requires a fundamental understanding of the coupling between phases. Though much progress has been made in this regard, there is still more to be done. One area that requires more research is the transport of electrons across the plasma-liquid interface. Some pioneering works (Rumbach et al 2015 Nat. Commun. 6, Rumbach et al 2015 J. Phys. D: Appl. Phys. 48 424001) have begun revealing the near-surface liquid characteristics of electrons. However, there has been little work to determine the near-surface gas phase electron characteristics. Without an understanding of the near-surface gas dynamics, modellers are left to make assumptions about the interfacial conditions. For instance it is commonly assumed that the surface loss or sticking coefficient of gas-phase electrons at the interface is equal to 1. In this work we explore the consequences of this assumption and introduce a couple of ways to think about the electron interfacial condition. In one set of simulations we impose a kinetic condition with varying surface loss coefficient on the gas phase interfacial electrons. In a second set of simulations we introduce a Henry's law like condition at the interface in which the gas-phase electron concentration is assumed to be in thermodynamic equilibrium with the liquid-phase electron concentration. It is shown that for a range of electron Henry coefficients spanning a range of known hydrophilic specie Henry coefficients, the gas phase electron density in the anode can vary by orders of magnitude. Varying reflection of electrons by the interface also has consequences for the electron energy profile; increasing reflection may lead to increasing thermalization of electrons depending on choices about the electron energy boundary condition. This variation in anode electron density and energy as a function of the interface characteristics could also lead to significant variation in near-surface gas chemistries when such reactions are included in the model; this could very well in turn affect the reactive species impinging on the liquid surface. We draw the conclusion that in order to make more confident model predictions about plasma-liquid systems, finer scale simulations and/or new experimental techniques must be used to elucidate the near-surface gas phase electron dynamics.},
	urldate = {2024-06-04},
	journal = {Journal of Physics D: Applied Physics},
	author = {Lindsay, Alexander D. and Graves, David B. and Shannon, Steven C.},
	month = may,
	year = {2016},
	file = {Fully coupled simulation of the plasma liquid interface and interfacial coefficient effects - IOPscience:/Users/huff/Zotero/storage/D45X28QG/meta.html:text/html},
}

@article{peterson_overview_2018,
	title = {Overview of the incompressible {Navier}{\textendash}{Stokes} simulation capabilities in the {MOOSE} framework},
	volume = {119},
	issn = {0965-9978},
	url = {https://www.sciencedirect.com/science/article/pii/S0965997817310591},
	doi = {10.1016/j.advengsoft.2018.02.004},
	abstract = {The Multiphysics Object Oriented Simulation Environment (MOOSE) framework is a high-performance, open source, C++ finite element toolkit developed at Idaho National Laboratory. MOOSE was created with the aim of assisting domain scientists and engineers in creating customizable, high-quality tools for multiphysics simulations. While the core MOOSE framework itself does not contain code for simulating any particular physical application, it is distributed with a number of physics {\textquotedblleft}modules{\textquotedblright} which are tailored to solving e.g. heat conduction, phase field, and solid/fluid mechanics problems. In this report, we describe the basic equations, finite element formulations, software implementation, and regression/verification tests currently available in MOOSE{\textquoteright}s navier\_stokes module for solving the Incompressible Navier-Stokes (INS) equations.},
	urldate = {2024-06-04},
	journal = {Advances in Engineering Software},
	author = {Peterson, John W. and Lindsay, Alexander D. and Kong, Fande},
	month = may,
	year = {2018},
	pages = {68--92},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/VVWJ385D/S0965997817310591.html:text/html;Submitted Version:/Users/huff/Zotero/storage/UHTMZNW4/Peterson et al. - 2018 - Overview of the incompressible Navier{\textendash}Stokes simul.pdf:application/pdf},
}

@article{lindsay_fertilization_2014,
	title = {Fertilization of {Radishes}, {Tomatoes}, and {Marigolds} {Using} a {Large}-{Volume} {Atmospheric} {Glow} {Discharge}},
	volume = {34},
	issn = {1572-8986},
	url = {https://doi.org/10.1007/s11090-014-9573-x},
	doi = {10.1007/s11090-014-9573-x},
	abstract = {A large-volume atmospheric glow discharge has been used to incorporate nitrogen species into aqueous solution that is subsequently used to fertilize radishes, marigolds, and tomatoes. Treatment with plasma activated water (PAW) was compared to a tap water control. Water application began immediately after seeding and continued for 4~weeks. At the conclusion of the experiment, PAW treated plants had shoot masses 1.7{\textendash}2.2 times larger than controls. Subsequent research has focused on optimizing the amount of nitrogen in solution by varying discharge power, air flow, air{\textendash}water interface, and water alkalinity. When the discharge hovers over a stationary water phase, nitrate concentrations increase with decreasing power and increasing air flow. When water droplets are injected directly into the plasma, nitrate concentrations increase with increasing power and decreasing air flow. These contrasting trends are believed to depend on the balance between hydroxyl and electron concentrations in the discharge. Adding NaHCO3 to water before plasma treatment affects both the amount of nitrogen present in solution as well as the ratio between oxidized and reduced species. Concentrated NaHCO3 solution had 2.9 times more total nitrogen, 59 times more nitrite, and 27~\% less nitrate after plasma treatment than a solution with no NaHCO3. Two factors could contribute to the spike in nitrite and decrease in nitrate: reaction of nitric and nitrous oxides with bicarbonate to form nitrite, and a decrease in disproportionation of nitrate that occurs readily at acidic pH but negligibly under neutral conditions.},
	language = {en},
	number = {6},
	urldate = {2024-06-04},
	journal = {Plasma Chemistry and Plasma Processing},
	author = {Lindsay, Alex and Byrns, Brandon and King, Wesley and Andhvarapou, Asish and Fields, Jeb and Knappe, Detlef and Fonteno, William and Shannon, Steven},
	month = nov,
	year = {2014},
	keywords = {Atmospheric pressure plasma, Fertilization, Large-volume glow, Reactive nitrogen and oxygen species},
	pages = {1271--1290},
	file = {Full Text PDF:/Users/huff/Zotero/storage/F8MYX9WW/Lindsay et al. - 2014 - Fertilization of Radishes, Tomatoes, and Marigolds.pdf:application/pdf},
}

@article{anderson_role_2016,
	title = {The {Role} of {Interfacial} {Reactions} in {Determining} {Plasma}{\textendash}{Liquid} {Chemistry}},
	volume = {36},
	issn = {1572-8986},
	url = {https://doi.org/10.1007/s11090-016-9742-1},
	doi = {10.1007/s11090-016-9742-1},
	abstract = {In this work, we investigate the production of highly oxidative species in solutions exposed to a self-pulsed corona discharge in air. We examine how the properties of the target solution (pH, conductivity) and the discharge power affect the discharge stability and the production of H2O2. Indigo carmine, a common organic dye, is used as an indicator of oxidative strength and in particular, hydroxyl radical (OH{\textperiodcentered}) production. The observed rate of indigo oxidation in contact with the discharge far exceeds that predicted from reactions based on concentrations of species measured in the bulk solution. The generation of H2O2 and the oxidation of indigo carmine indicate a high concentration of highly oxidizing species such as OH{\textperiodcentered} at the plasma{\textendash}liquid interface. These results indicate that reactions at the air plasma{\textendash}liquid interface play a dominant role in species oxidation during direct non-equilibrium atmospheric pressure plasma treatment.},
	language = {en},
	number = {6},
	urldate = {2024-06-04},
	journal = {Plasma Chemistry and Plasma Processing},
	author = {Anderson, Carly E. and Cha, Nico R. and Lindsay, Alexander D. and Clark, Douglas S. and Graves, David B.},
	month = nov,
	year = {2016},
	keywords = {Corona discharge, Indigo carmine, Non-equilibrium atmospheric pressure plasma (NEAPP), Plasma activated water (PAW), Reactive oxygen species},
	pages = {1393--1415},
	file = {Full Text PDF:/Users/huff/Zotero/storage/E2AA8HWX/Anderson et al. - 2016 - The Role of Interfacial Reactions in Determining P.pdf:application/pdf},
}

@article{lindsay_20_2022,
	title = {2.0 - {MOOSE}: {Enabling} massively parallel multiphysics simulation},
	volume = {20},
	issn = {2352-7110},
	shorttitle = {2.0 - {MOOSE}},
	url = {https://www.sciencedirect.com/science/article/pii/S2352711022001200},
	doi = {10.1016/j.softx.2022.101202},
	abstract = {The last 2 years have been a period of unprecedented growth for the MOOSE community and the software itself. The number of monthly visitors to the website has grown from just over 3,000 to now averaging 5,000. In addition, over 1,800 pull requests have been merged since the beginning of 2020, and the new discussions forum has averaged 600 unique visitors per month. The previous publication has been cited over 200 times since it was published 2 years ago. This paper serves as an update on some of the key additions and changes to the code and ecosystem over the last 2 years, as well as recognizing contributions from the community.},
	urldate = {2024-06-04},
	journal = {SoftwareX},
	author = {Lindsay, Alexander D. and Gaston, Derek R. and Permann, Cody J. and Miller, Jason M. and Andr{\v s}, David and Slaughter, Andrew E. and Kong, Fande and Hansel, Joshua and Carlsen, Robert W. and Icenhour, Casey and Harbour, Logan and Giudicelli, Guillaume L. and Stogner, Roy H. and German, Peter and Badger, Jacob and Biswas, Sudipta and Chapuis, Leora and Green, Christopher and Hales, Jason and Hu, Tianchen and Jiang, Wen and Jung, Yeon Sang and Matthews, Christopher and Miao, Yinbin and Novak, April and Peterson, John W. and Prince, Zachary M. and Rovinelli, Andrea and Schunert, Sebastian and Schwen, Daniel and Spencer, Benjamin W. and Veeraraghavan, Swetha and Recuero, Antonio and Yushu, Dewen and Wang, Yaqi and Wilkins, Andy and Wong, Christopher},
	month = dec,
	year = {2022},
	keywords = {Finite-element, Framework, Multiphysics, Object-oriented},
	pages = {101202},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/8TCAVQRV/S2352711022001200.html:text/html;Submitted Version:/Users/huff/Zotero/storage/H93MHKNC/Lindsay et al. - 2022 - 2.0 - MOOSE Enabling massively parallel multiphys.pdf:application/pdf},
}

@article{lindsay_momentum_2015,
	title = {Momentum, heat, and neutral mass transport in convective atmospheric pressure plasma-liquid systems and implications for aqueous targets},
	volume = {48},
	issn = {0022-3727},
	url = {https://dx.doi.org/10.1088/0022-3727/48/42/424007},
	doi = {10.1088/0022-3727/48/42/424007},
	abstract = {There is a growing interest in the study of plasma-liquid interactions with application to biomedicine, chemical disinfection, agriculture, and other fields. This work models the momentum, heat, and neutral species mass transfer between gas and aqueous phases in the context of a streamer discharge; the qualitative conclusions are generally applicable to plasma-liquid systems. The problem domain is discretized using the finite element method. The most interesting and relevant model result for application purposes is the steep gradients in reactive species at the interface. At the center of where the reactive gas stream impinges on the water surface, the aqueous concentrations of OH and ONOOH decrease by roughly 9 and 4 orders of magnitude respectively within 50 m of the interface. Recognizing the limited penetration of reactive plasma species into the aqueous phase is critical to discussions about the therapeutic mechanisms for direct plasma treatment of biological solutions. Other interesting results from this study include the presence of a 10 K temperature drop in the gas boundary layer adjacent to the interface that arises from convective cooling. Though the temperature magnitudes may vary among atmospheric discharge types (different amounts of plasma-gas heating), this relative difference between gas and liquid bulk temperatures is expected to be present for any system in which convection is significant. Accounting for the resulting difference between gas and liquid bulk temperatures has a significant impact on reaction kinetics; factor of two changes in terminal aqueous species concentrations like H2O2, NO, and NO are observed in this study if the effect of evaporative cooling is not included.},
	language = {en},
	number = {42},
	urldate = {2024-06-04},
	journal = {Journal of Physics D: Applied Physics},
	author = {Lindsay, Alexander and Anderson, Carly and Slikboer, Elmar and Shannon, Steven and Graves, David},
	month = sep,
	year = {2015},
	note = {Publisher: IOP Publishing},
	pages = {424007},
	file = {IOP Full Text PDF:/Users/huff/Zotero/storage/6NQWCS8H/Lindsay et al. - 2015 - Momentum, heat, and neutral mass transport in conv.pdf:application/pdf},
}

@inproceedings{alhassan_estimation_2024,
	title = {{ESTIMATION} {OF} {GAMMA} {HEAT} {DEPOSITION} {IN} {FUEL} {AND} {NON}- {FUEL} {MATERIALS} {IN} {SUPPORT} {OF} {IRRADIATION} {OF} {MEDICAL} {RADIOISOTOPES} {IN} {BR2} {REACTOR}},
	abstract = {For the design of capsules and targets for irradiation, the heat generated within different reactor locations and materials must be determined for the purpose of ensuring the safety and integrity of capsules and targets. In this work, neutron and gamma heating calculations were carried out in both fissile and non-fissile materials within the Belgian Reactor-2 reactor using the MCNP6 code, taking into account, both the prompt gamma heating i.e. gamma heating caused by the photons emitted right after neutron interaction in the fuel (and/or structural materials) and, delayed gamma heating coming from decays of activation and fission products as well as decay of non-fuel materials. The delayed gamma contribution was obtained by using an additional calculation with the so-called PIKMT card. In addition, we demonstrate that the choice of nuclear data library has impact on the estimated heat deposited by replacing the nuclear data of all isotopes within the reactor with the ENDF/B-VIII.0, ENDF/B-VII.1 and the JENDL5.0 nuclear data libraries.},
	author = {Alhassan, Erwin and Sikik, E and Kalcheva, Silva and Newman, G and Hernandez-Solis, A and Wols, F and Van Dyck, Steven and Van den Branden, Geert and Rykhlevskii, A},
	month = apr,
	year = {2024},
}

@misc{rykhlevskii_comparing_2019,
	title = {Comparing fast neutron transport calculations using code package {KATRIN}-2.0 for various options of {VVER}-440 core setup},
	url = {https://engrxiv.org/preprint/view/396},
	doi = {10.31224/osf.io/b6k4f},
	language = {en},
	urldate = {2024-06-03},
	publisher = {Engineering Archive},
	author = {Rykhlevskii, Andrei and Tsofin, Vladimir},
	month = jan,
	year = {2019},
	keywords = {neutron fluence, neutron transport, vver},
	file = {Full Text PDF:/Users/huff/Zotero/storage/Q2ZGKARU/Rykhlevskii and Tsofin - 2019 - Comparing fast neutron transport calculations usin.pdf:application/pdf},
}

@techreport{rykhlevskii_mitr_2023,
	title = {{MITR} \& {NBSR} {DDE} {Irradiations} in {BR2}{\textendash}{Fluence} in {LEU} {Cladding} and {Structural} {Materials}},
	url = {https://www.osti.gov/servlets/purl/1969641},
	number = {ANL/RTR/TM-22/25},
	urldate = {2024-06-03},
	institution = {Argonne National Lab.(ANL), Argonne, IL (United States)},
	author = {Rykhlevskii, Andrei and Bergeron, Aurelien and Puig, Francesc},
	year = {2023},
	file = {Available Version (via Google Scholar):/Users/huff/Zotero/storage/LYUUYITQ/Rykhlevskii et al. - 2023 - MITR & NBSR DDE Irradiations in BR2{\textendash}Fluence in LEU.pdf:application/pdf},
}

@incollection{rykhlevskii_chapter_2024,
	series = {Woodhead {Publishing} {Series} in {Energy}},
	title = {Chapter 26 - {Kairos} power pebble bed reactor},
	isbn = {978-0-323-99355-5},
	url = {https://www.sciencedirect.com/science/article/pii/B9780323993555000100},
	abstract = {The Kairos Power reactor has a circular cylindrical core of ping-pong-ball-size graphite {\textquotedblleft}pebbles{\textquotedblright} floating in molten FliBe coolant salt. Each pebble contains large numbers of tiny spheres of UCO encapsulated by layers of SiC and pyrolytic graphite. The pebbles can operate at extremely high temperatures without damage, so high coolant temperatures can yield 45\% efficiency of electricity generation. The low-pressure operation allows thin vessel and piping, much safer and less expensive than the high-pressure vessels of water-cooled or helium-cooled reactor systems.},
	urldate = {2024-06-03},
	booktitle = {Molten {Salt} {Reactors} and {Thorium} {Energy} ({Second} {Edition})},
	publisher = {Woodhead Publishing},
	author = {Rykhlevskii, Andrei},
	editor = {Dolan, Thomas James and P{\'a}zsit, Imre and Rykhlevskii, Andrei and Yoshioka, Ritsuo},
	month = jan,
	year = {2024},
	doi = {10.1016/B978-0-323-99355-5.00010-0},
	keywords = {fluoride salt, high-temperature, Molten salt reactor, online refueling, solid fuel, TRISO},
	pages = {945--952},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/CT3ED9MB/B9780323993555000100.html:text/html},
}

@inproceedings{chaube_natural_2023,
	title = {Natural {Convection} {CFD} {Modeling} of a {Microreactor} {Air} {Jacket}: 2023 {Transactions} of the {American} {Nuclear} {Society} {Winter} {Conference} and {Expo}, {ANS} 2023},
	volume = {129},
	shorttitle = {Natural {Convection} {CFD} {Modeling} of a {Microreactor} {Air} {Jacket}},
	url = {http://www.scopus.com/inward/record.url?scp=85180623501&partnerID=8YFLogxK},
	doi = {10.13182/T129-42905},
	urldate = {2024-06-03},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	author = {Chaube, Anshuman and Novak, April and Shaver, Dillon and Brooks, Caleb},
	year = {2023},
	pages = {948--951},
}

@techreport{shemon_development_2023,
	title = {Development and {Porting} of {Nuclear} {Reactor} {Computational} {Models} for the {NRIC} {Virtual} {Test} {Bed} in {FY23}},
	url = {https://www.osti.gov/biblio/1999614},
	abstract = {The U.S. DOE{\textquoteright}s National Reactor Innovation Center (NRIC) hosts an open-source website and associated GitHub repository called the Virtual Test Bed (VTB) on which computational models for advanced reactors are documented and shared with the reactor community. In FY23 under the NRIC program, computational models for nuclear reactor analysis were developed and contributed to the VTB Github repository during FY23 by contributors at Argonne National Laboratory. Other models developed outside of NRIC were also ported to the VTB as part of this work, serving a broader mission to make computational reactor analysis models more widely available to the reactor community. The model development activities focused on demonstration of gas-cooled microreactor models including computational fluid dynamics simulations of flow through an industry-inspired air jacket design, and simulation of multiphysics transients for a gas-cooled microreactor assembly. Additionally, development of a molten salt reactor (led at Idaho National Laboratory) was supported through Argonne{\textquoteright}s expertise in multigroup cross sections generation. Models for these two reactor types were targeted due to their relevancy to NRIC{\textquoteright}s Demonstration of Microreactor Experiments (DOME) and Laboratory for Operation and Testing in the U.S. (LOTUS) physical test beds, which are slated to host microreactor and molten salt reactor experiments. The model porting activities consisted of developing detailed documentation for several physics models which originate from the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program. We include only contributions from Argonne National Laboratory in this report.},
	language = {English},
	number = {ANL/NSE-23/51},
	urldate = {2024-06-03},
	institution = {Argonne National Laboratory (ANL), Argonne, IL (United States)},
	author = {Shemon, Emily and Abdelhameed, Ahmed and Chaube, Anshuman and Fang, Jun and Fei, Tingzhou and Hua, Thanh and Lee, Changho and Novak, April and Ooi, Zhiee and Shaver, Dillon and Stauff, Nicolas and Wozniak, Nicholas and Zou, Ling},
	month = sep,
	year = {2023},
	doi = {10.2172/1999614},
	file = {Full Text PDF:/Users/huff/Zotero/storage/9RDZDK3I/Shemon et al. - 2023 - Development and Porting of Nuclear Reactor Computa.pdf:application/pdf},
}

@article{chaube_nuclear_2024,
	title = {Nuclear microreactors and thermal integration with hydrogen generation processes},
	volume = {419},
	issn = {0029-5493},
	url = {https://www.sciencedirect.com/science/article/pii/S0029549324000700},
	doi = {10.1016/j.nucengdes.2024.112968},
	abstract = {Nuclear microreactors offer reliable, low-carbon dispatchable power and heat for various end use applications. Although the direct electricity end uses are straightforward, the feasibility of microreactors{\textquoteright} integration for thermal end use has not been analyzed in literature in sufficient detail. Delivering process heat generated by nuclear microreactors to supply the high temperatures essential for hydrogen production has been proposed as one cogeneration option that can further aid in the alleviation of climate change, since hydrogen can replace carbon-emitting fuels such as gasoline, diesel or natural gas. This review provides a novel perspective on the intersection of microreactors and process heat use by investigating hydrogen production technologies, microreactor designs and process heat integration options. A comprehensive overview of hydrogen production methods including electrolysis and thermochemical conversions of hydrocarbons and water is presented by classifying the methods based on process temperatures and maturity. Additionally, an in-depth summary detailing the reactor type, power output, and maximum operating temperature of many prospective microreactor designs has been created. Finally, heat transfer options for integrating microreactors to hydrogen production systems were evaluated. The intermediate heat exchanger (IHX) assessment considers IHX material, IHX type, and heat transfer media utilized within the apparatus.},
	urldate = {2024-06-03},
	journal = {Nuclear Engineering and Design},
	author = {Chaube, Anshuman and Ahmed, Zayed and Sieh, Broderick and Brooks, Caleb S. and Bindra, Hitesh},
	month = apr,
	year = {2024},
	keywords = {Hydrogen, Microreactors, Nuclear hybrid systems, Thermochemical integration},
	pages = {112968},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/P3HS5EYA/S0029549324000700.html:text/html},
}

@article{permann_moose_2020,
	title = {{MOOSE}: {Enabling} massively parallel multiphysics simulation},
	volume = {11},
	issn = {23527110},
	shorttitle = {{MOOSE}},
	url = {https://linkinghub.elsevier.com/retrieve/pii/S2352711019302973},
	doi = {10.1016/j.softx.2020.100430},
	abstract = {Semantic Scholar extracted view of "MOOSE: Enabling Massively Parallel Multiphysics Simulation" by C. Permann et al.},
	language = {en},
	urldate = {2024-06-03},
	journal = {SoftwareX},
	author = {Permann, Cody J. and Gaston, Derek R. and Andr{\v s}, David and Carlsen, Robert W. and Kong, Fande and Lindsay, Alexander D. and Miller, Jason M. and Peterson, John W. and Slaughter, Andrew E. and Stogner, Roy H. and Martineau, Richard C.},
	month = jan,
	year = {2020},
	pages = {100430},
	file = {Full Text PDF:/Users/huff/Zotero/storage/LBXVPN5L/Permann et al. - 2020 - MOOSE Enabling massively parallel multiphysics si.pdf:application/pdf},
}

@article{seifert_simple_nodate,
	title = {Simple {Flexible} {Molten} {Salt} {Reactor}},
	language = {en},
	author = {Seifert, Luke and Boettinger, Alex and Breakell, Jackson and Wooden, Patrick},
	file = {Seifert et al. - Simple Flexible Molten Salt Reactor.pdf:/Users/huff/Zotero/storage/M9W4J67L/Seifert et al. - Simple Flexible Molten Salt Reactor.pdf:application/pdf},
}

@article{seifert_simple_2020,
	title = {Simple {Flexible} {Molten} {Salt} {Reactor}},
	url = {https://trace.tennessee.edu/utk_chanhonoproj/2383},
	journal = {Chancellor{\textquoteright}s Honors Program Projects},
	author = {Seifert, Luke and Boettinger, Alex and Breakell, Jackson and Wooden, Patrick},
	month = may,
	year = {2020},
	file = {"Simple Flexible Molten Salt Reactor" by Luke Seifert, Alex Boettinger et al.:/Users/huff/Zotero/storage/DK49ZBRR/2383.html:text/html},
}

@phdthesis{seifert_analysis_2023,
	type = {Thesis},
	title = {Analysis of and comparison between reprocessing methods in the molten salt breeder reactor},
	copyright = {Copyright 2023 Luke Seifert},
	url = {https://hdl.handle.net/2142/122029},
	abstract = {Liquid fueled molten salt reactor modeling can be challenging, as the fuel composition varies temporally and spatially. Although these models are challenging, they are important for predicting reactor safety and performance during operation. One of the reasons these models are challenging is the difficulty in capturing different physical phenomena which occur in different time scales. Over short time scales, one of these physical phenomena is the movement of delayed neutron precursors to less important regions of the reactor.
For longer time scales, one of these physical phenomena is online reprocessing, which includes adding fresh fuel and removing fission products from the reactor during operation and is the focus of this work. Reprocessing is useful in liquid fueled molten salt reactors because it limits chemical corrosion and improves the neutron economy. Reprocessing can be performed continuously during operation, referred to as online reprocessing, or in batches during outages, referred to as batchwise reprocessing. In order to simulate reprocessing computationally, there are two different mathematical approaches which are commonly implemented in the literature, called batchwise and continuous reprocessing. The continuous reprocessing method is more physically reflective of reactors using a chemically continuous reprocessing scheme. However, there are many works which have implemented batchwise reprocessing methods to simulate a physically continuous reprocessing process. In this thesis, I show that continuous reprocessing and batchwise reprocessing methods are not interchangeable. Using both methods on the same system shows that there are non-trivial differences in the results. I also investigate the computational cost of different reprocessing methods by performing a depletion time step refinement study. In this study, I found that continuous reprocessing allows for significantly larger time steps without large increases in error, which reduces computational cost. However, continuous reprocessing does not necessarily keep the overall mass constant, thus potentially leading to a nonphysical solution. I compare the differences between both methods while determining the effect of this nonphysical mass change caused by continuous reprocessing.},
	urldate = {2024-06-03},
	school = {University of Illinois at Urbana-Champaign},
	author = {Seifert, Luke},
	month = dec,
	year = {2023},
	file = {Full Text PDF:/Users/huff/Zotero/storage/PCNX244X/Seifert - 2023 - Analysis of and comparison between reprocessing me.pdf:application/pdf},
}

@article{yardas_runaway_nodate,
	title = {Runaway electron seed population dependence on temperature profile using continuous electric field evolution},
	language = {en},
	author = {Yardas, Oleksandr R and Embreus, Ola and Liu, Chang and Brennan, Dylan P},
	file = {Yardas et al. - Runaway electron seed population dependence on tem.pdf:/Users/huff/Zotero/storage/PKSDWZHN/Yardas et al. - Runaway electron seed population dependence on tem.pdf:application/pdf},
}

@inproceedings{ridley_preliminary_2017,
	title = {Preliminary {Results} of {Material} {Flow} {Controlled} {MSR} {Depletion} {Calculations}},
	volume = {116},
	url = {https://www.osti.gov/biblio/23050345},
	abstract = {A versatile, parallelizable Python 2.7 library was developed in order to simulate once-through molten salt reactor depletion in a realistic manner via the coupled neutronics/depletion code Serpent 2. Realistic in this sense entails two aspects: reactivity of the core, and oxidation potential of the fuel. The core reactivity should be maintained near zero as with any nuclear reactor. Gross reactivity control is provided by variations of the refuel rate of the reactor. Fine reactivity adjustments are expected to be done with control mechanisms in real-life power operation. The Python library developed allows a user to set bounds on the desired ke f f value. Fuel oxidation potential must be controlled for any liquid fueled reactor. As a simple example, consider this fission where the fuel becomes more oxidizing: UF\{sub 4\} {\textrightarrow} SrF\{sub 2\} + Xe + 2F\{sup -\} It can be shown using expected fission product oxidation state data that for these reactors, the fuel will become more oxidizing over time as a result of accumulation of excess fluoride ion. Addition of a reducing agent to reactor fuel will be necessary in the operation of molten salt reactors.},
	language = {English},
	urldate = {2024-06-03},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	author = {Ridley, Gavin and Chvala, Ondrej},
	month = jul,
	year = {2017},
	file = {Snapshot:/Users/huff/Zotero/storage/RLMQZKUV/23050345.html:text/html},
}

@inproceedings{floyd_concept_2018,
	title = {Concept {Reactor} for {Extraterrestrial} {Surface} {Power}: {PULSR}},
	volume = {119},
	url = {https://epubs.ans.org/?a=44151&_gl=1*1tiiuor*_ga*MTUyMzM4MzE2Ny4xNzE3MTkwNDY2*_ga_FZ1DECQ83C*MTcxNzQ0OTc4MC4zLjEuMTcxNzQ1Mjc1NC4wLjAuMA..},
	abstract = {The production of power in extraterrestrial environments
is a topic of interest for furthering space exploration. An extraterrestrial power reactor would be able to produce necessary energy for robotic equipment for an exploration colony.
This has lead to an interest in implementing nuclear energy
for surface power during extraterrestrial missions, particularly noteworthy being NASA{\textquoteright}s efforts towards the Kilopower
reactor [1]. As the reactor is located in space, there are a number of constraints that need to be placed upon the design of the
reactor. Specifically, the reactor needs to be both lightweight
and highly reliable over its entire operation lifetime.
To achieve low mass and lengthy operation, highly fissile
plutonium-239 based fuel operating in a semi-fast spectrum
was chosen. Such fuel, in addition to enabling low startup
critical mass, could be employed to partially fulfill the obligations made in the 2001 plutonium disposition and management agreement [2]. Because of this, a new low mass space
reactor concept has been developed to provide 20kW(t) over a
20 year long mission to the Martian surface. This reactor design is known as the Plutonium Ultra-Light Surface Reactor
or PULSR for short, generally illustrated by Figure 1.},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	publisher = {American Nuclear Society},
	author = {Floyd, Dan and Ridley, Gavin and Tidwell, Patrick and Tebbs, Walter},
	month = nov,
	year = {2018},
	pages = {62--65},
}

@article{ridley_simple_2021,
	title = {A simple method for rejection sampling efficiency improvement on {SIMT} architectures},
	volume = {31},
	issn = {1573-1375},
	url = {https://doi.org/10.1007/s11222-021-10003-z},
	doi = {10.1007/s11222-021-10003-z},
	abstract = {We derive a probability distribution for the possible number of iterations required for a SIMT (single instruction multiple thread) program using rejection sampling to finish creating a sample across all threads. This distribution is found to match a recently proposed distribution from Chakraborty and Gupta (in: Communications in statistics: theory and methods, 2015) that was shown as a good approximation of certain datasets. This work demonstrates an exact application of this distribution. The distribution can be used to evaluate the relative merit of some sampling methods on the GPU without resort to numerical tests. The distribution reduces to the expected geometric distribution in the single thread per warp limit. A simplified formula to approximate the expected number of iterations required to obtain rejection iteration samples is provided. With this new result, a simple, efficient layout for assigning sampling tasks to threads on a GPU is found as a function of the rejection probability without recourse to more complicated rejection sampling methods.},
	language = {en},
	number = {3},
	urldate = {2024-06-03},
	journal = {Statistics and Computing},
	author = {Ridley, Gavin and Forget, Benoit},
	month = mar,
	year = {2021},
	keywords = {Distributions, Graphics processing units, Monte Carlo, Parallel computing, Rejection sampling, SIMT},
	pages = {30},
	file = {Full Text PDF:/Users/huff/Zotero/storage/DYCBS543/Ridley and Forget - 2021 - A simple method for rejection sampling efficiency .pdf:application/pdf},
}

@article{gaston_method_2021,
	title = {Method of {Characteristics} for {3D}, {Full}-{Core} {Neutron} {Transport} on {Unstructured} {Mesh}},
	volume = {207},
	issn = {0029-5450},
	url = {https://doi.org/10.1080/00295450.2021.1871995},
	doi = {10.1080/00295450.2021.1871995},
	abstract = {A myriad of nuclear reactor designs are currently being considered for next-generation power production. These designs utilize unique geometries and materials and can rely on multiphysics effects for safety and operation. This work develops a neutron transport tool, MOCkingbird, capable of three-dimensional (3D), full-core reactor simulation for previously intractable geometries. The solver is based on the method of characteristics, utilizing unstructured mesh for the geometric description. MOCkingbird is built using the MOOSE multiphysics framework, allowing for straightforward linking to other physics in the future. A description of the algorithms and implementation is given, and solutions are computed for two-dimensional/3D C5G7 and the Massachusetts Institute of Technology BEAVRS benchmark. The final result shows the application of MOCkingbird to a 3D, full-core simulation utilizing 1.4 billion elements and solved using 12~000 processors.},
	number = {7},
	urldate = {2024-06-03},
	journal = {Nuclear Technology},
	author = {Gaston, Derek R. and Forget, Benoit and Smith, Kord S. and Harbour, Logan H. and Ridley, Gavin K. and Giudicelli, Guillaume G.},
	month = jul,
	year = {2021},
	note = {Publisher: Taylor \& Francis
\_eprint: https://doi.org/10.1080/00295450.2021.1871995},
	keywords = {Method of characteristics, MOCkingbird, MOOSE, BEAVRS, unstructured mesh},
	pages = {931--953},
	file = {Full Text PDF:/Users/huff/Zotero/storage/2QFDPWUF/Gaston et al. - 2021 - Method of Characteristics for 3D, Full-Core Neutro.pdf:application/pdf},
}

@article{johnson_serpenttools_2020,
	title = {{serpentTools}: {A} {Python} {Package} for {Expediting} {Analysis} with {Serpent}},
	volume = {194},
	issn = {0029-5639},
	shorttitle = {{serpentTools}},
	url = {https://doi.org/10.1080/00295639.2020.1723992},
	doi = {10.1080/00295639.2020.1723992},
	abstract = {The serpentTools Python package is presented as a useful and efficient alternative for processing Serpent results. One positive attribute of Serpent is that many output files are exported directly in a MATLAB format, allowing for results to be loaded with minimal to no effort. However, some files for larger analyses may require immense amounts of memory to load and store all the data, leading to long wait times. To expedite the process of data handling and ease common analyses, the Computational Reactor Engineering lab at the Georgia Institute of Technology has released and is maintaining the serpentTools Python package: a set of data parsers and containers intended to streamline analysis with Serpent outputs. The parsers are capable of processing large outputs with ease, and yield all data to the user in a simple object-oriented framework. Data can be read into Python in comparable or better times than MATLAB, with the option to store only data needed for a specific purpose. Furthermore, common analyses are implemented directly into the package to expedite frequent analysis, including plotting meshed data and flux specta. serpentTools is designed to be a useful and practical manner by which the Serpent community can load and analyze data inside a Python environment. This paper presents the Python package, highlighting some basic features, and compares capabilities to similar platforms.},
	number = {11},
	urldate = {2024-06-03},
	journal = {Nuclear Science and Engineering},
	author = {Johnson, Andrew E. and Kotlyar, Dan and Terlizzi, Stefano and Ridley, Gavin},
	month = nov,
	year = {2020},
	note = {Publisher: Taylor \& Francis
\_eprint: https://doi.org/10.1080/00295639.2020.1723992},
	keywords = {open source, visualization, Python, Serpent},
	pages = {1016--1024},
	file = {Full Text PDF:/Users/huff/Zotero/storage/UADDQT65/Johnson et al. - 2020 - serpentTools A Python Package for Expediting Anal.pdf:application/pdf},
}

@article{ridley_method_2017,
	title = {A method for predicting fuel maintenance in once-through {MSRs}},
	volume = {110},
	issn = {0306-4549},
	url = {https://www.sciencedirect.com/science/article/pii/S030645491730021X},
	doi = {10.1016/j.anucene.2017.06.043},
	abstract = {Liquid fuel molten salt reactors allow reactivity control by material addition. This paper presents a method to adjust material flows in a molten salt reactor to keep the core critical, and to maintain desired reduction-oxidation potential in the core salt melt. The method is aimed at low-enriched uranium fueled thermal systems. It is developed as a Python library and uses Serpent2 Monte-Carlo transport and depletion code. A toy 300MW(th) reactor with a FLiBe carrier salt is employed to demonstrate the performance of the method over 10 full power years. Results of the calculation are presented, including material flows, conversion ratio, effective delayed neutron fraction, and expected limits on trifluoride concentrations and graphite lifetime are investigated. This method lays a foundation for future studies including fuel cycle performance of molten salt reactors and dynamic behavior of the core during depletion.},
	urldate = {2024-06-03},
	journal = {Annals of Nuclear Energy},
	author = {Ridley, Gavin and Chvala, Ondrej},
	month = dec,
	year = {2017},
	keywords = {Chemistry control, Depletion, DMSR, Molten salt reactor, On-line refueling, Serpent},
	pages = {265--281},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/SLRST9UA/S030645491730021X.html:text/html},
}

@inproceedings{ridley_design_nodate,
	title = {Design and {Optimization} of {GPU} {Capabilities} in {OpenMC}},
	url = {https://www.ans.org/meetings/wm2021/session/view-833/},
	author = {Ridley, Gavin and Forget, Benoit},
}

@inproceedings{ridley_transient_2022,
	series = {Proceedings of the {International} {Conference} on {Physics} of {Reactors}, {PHYSOR} 2022},
	title = {Transient {MOC} with {Frequency} {Transform} and {DSA} on {Unstructured} {Mesh}: 2022 {International} {Conference} on {Physics} of {Reactors}, {PHYSOR} 2022},
	shorttitle = {Transient {MOC} with {Frequency} {Transform} and {DSA} on {Unstructured} {Mesh}},
	url = {http://www.scopus.com/inward/record.url?scp=85184961113&partnerID=8YFLogxK},
	doi = {10.13182/PHYSOR22-37605},
	abstract = {We present an implementation of the transient method of characteristics (MOC) with isotropic time derivatives, accelerated by diffusion synthetic acceleration. The fully implicit frequency transform method is used to solve the transient problem with analytic precursor integration. The code works on meshes composed of almost any of the commonly used non-curvilinear finite element types, and can handle the deformation of geometry in time-dependent transport calculations. We present results of a continuous Fourier analysis for the transient multigroup DSA problem, and representative benchmarking results are presented for the C5G7-TD benchmark in 2D showing reasonable performance and agreement compared to other codes.},
	urldate = {2024-06-03},
	booktitle = {Proceedings of the {International} {Conference} on {Physics} of {Reactors}, {PHYSOR} 2022},
	author = {Ridley, Gavin and Harbour, Logan and Forget, Benoit and Gaston, Derek},
	year = {2022},
	note = {Publisher: American Nuclear Society},
	pages = {430--439},
	annote = {Funding Information:This material is based upon work supposed by a Department of Energy Nuclear Energy University Programs Graduate Fellowship. This research made use of Idaho National Laboratory computing resources which are supported by the Office of Nuclear Energy and the Nuclear Science User Facilities under Contract No. DE-AC07-05ID14517.Publisher Copyright:{\textcopyright} 2022 Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. All Rights Reserved.},
}

@inproceedings{forget_performance_2022,
	address = {United States},
	title = {Performance improvements of the windowed multipole formalism using a rational fraction approximation of the {Faddeeva} function},
	isbn = {978-0-89448-787-3},
	url = {https://inis.iaea.org/search/search.aspx?orig_q=RN:54002337},
	abstract = {The windowed multipole (WMP) formalism was introduced as a way to calculate Doppler
broadened cross sections on the fly during Monte Carlo simulations While more arithmetic
is needed compared to point-wise cross section look-ups, performance remained competitive
from the large memory reductions and sequential data access The single most expensive
function call in a depleted fuel assembly problem using WMP comes from the evaluation
of the Faddeeva function, which previously relied on a highly accurate, highly-branching
algorithm This paper explores the use of rational fraction approximations tailored
to the domain interest of reactor physics applications and the development of lower
accuracy approximations sufficient for our application The rational approximations
were implemented and tested in OpenMC on an infinite medium problem to stress the
cross section calculation routine and a PWR assembly problem In both cases, the rational
approximation nearly eliminated the \~{} 20\% penalty previously observed when comparing
to point-wise libraries (authors)},
	booktitle = {Proceedings of the international conference on physics of reactors - {PHYSOR} 2022},
	publisher = {ANS - American Nuclear Society},
	author = {Forget, B. and Yu, J. and Ridley, G.},
	year = {2022},
	note = {INIS Reference Number: 54002337},
}

@inproceedings{tramm_toward_2022,
	address = {Pittsburg, PA},
	title = {Toward {Portable} {GPU} {Acceleration} of the {OpenMC} {Monte} {Carlo} {Particle} {Transport} {Code}},
	url = {https://www.ans.org/pubs/proceedings/article-51248/},
	doi = {doi.org/10.13182/PHYSOR22-37847},
	abstract = {OpenMC is an open source Monte Carlo particle transport code originally designed for CPUbased systems. In this work, we use the OpenMP target offload p rogramming m odel t o port
OpenMC to a variety of GPU architectures from NVIDIA and AMD. We detail our porting strategy and provide preliminary performance comparisons. The GPU version of OpenMC run on an
NVIDIA A100 GPU achieves performance equivalent to approximately 200 Xeon CPU cores for
a depleted fuel reactor benchmark problem},
	urldate = {2024-06-03},
	booktitle = {Proceedings of the {International} {Conference} on {Physics} of {Reactors} 2022 ({PHYSOR} 2022)},
	publisher = {American Nuclear Society},
	author = {Tramm, John R. and Romano, Paul K. and Doerfert, Johannes and Lund, Amanda L. and Shriwise, Patrick C. and Siegel, Andrew R. and Ridley, Gavin and Pastrello, Andrew},
	month = may,
	year = {2022},
	pages = {2734--2743},
	file = {Proceedings -- ANS / Publications / Proceedings:/Users/huff/Zotero/storage/LNP5ZKL3/article-51248.html:text/html},
}

@inproceedings{ridley_topologically_2022,
	address = {Anaheim, CA, United States},
	title = {Topologically {Optimal} {Nuclear} {Core} {Designs} using {Deterministic} {Neutronics}},
	url = {https://epubs-ans-org.proxy2.library.illinois.edu/?a=51549&_gl=1*exljsi*_ga*MTUyMzM4MzE2Ny4xNzE3MTkwNDY2*_ga_FZ1DECQ83C*MTcxNzQ0OTc4MC4zLjEuMTcxNzQ0OTgwNy4wLjAuMA..},
	abstract = {Additive manufacturing (AM) is currently used for high
value, high complexity parts across most manufacturing sectors. AM offers order-of-magnitude faster prototyping and
development timelines and the ability to manufacture complex geometries that combine multiple components into single
parts or create high performance components that cannot be
traditionally manufactured.
The Transformational Reactor Program (TCR) at Oak
Ridge National Laboraty has developed additive techniques
for nuclear reactor manufacturing focused on High Temperature Gas-cooled Reactor (HTGR) technologies. TCR{\textquoteright}s key
achievement is process development of AM fuel blocks using
TRISO fuel in a SiC matrix with arbitrary fuel form factors and
cooling channels. Notably, the fuel achieves a 60\% TRISO
packing fraction compared to the previous state of the art
of 40\% [1]. TCR has characterized AM SS 316L and AM
SiC [2] in high temperature and radiation environments and
consequently evidenced that AM materials are as viable as
traditionally manufactured materials in nuclear environments,
moreover exceeding performance of traditional manufacturing. AM{\textquoteright}s tool chest [3] for reactor design includes effectively
arbitrarily gradated core compositions, shaped coolant geometries, high packing fraction TRISO-matrix fuels, embedded
burnable poisons, and embedded sensors.},
	urldate = {2024-06-03},
	publisher = {American Nuclear Society},
	author = {Ridley, Gavin and Venneri, Lorenzo and Forget, Benoit},
	month = jun,
	year = {2022},
	file = {ANS / Digital Nuclear Library / Transactions / Volume 126 / Number 1 / Pages 764-767:/Users/huff/Zotero/storage/944KXE6D/epubs-ans-org.proxy2.library.illinois.edu.html:text/html},
}

@article{ridley_resonance_2024,
	title = {Resonance {Scattering} {Treatment} with the {Windowed} {Multipole} {Formalism}},
	copyright = {{\textcopyright} 2023 The Author(s). Published with license by Taylor \& Francis Group, LLC.},
	issn = {0029-5639},
	url = {https://ans.tandfonline.com/doi/abs/10.1080/00295639.2023.2204810},
	abstract = {A new method for directly sampling the resonance upscattering effect is presented. Alternatives have relied on inefficient rejection sampling techniques or large tabular storage of relative velocit...},
	language = {EN},
	urldate = {2024-06-03},
	journal = {Nuclear Science and Engineering},
	author = {Ridley, Gavin and Forget, Benoit and Burke, Timothy},
	month = mar,
	year = {2024},
	note = {Publisher: Taylor \& Francis},
	file = {Snapshot:/Users/huff/Zotero/storage/3UY44M56/00295639.2023.html:text/html},
}

@article{fairhurst-agosta_delayed_2024,
	title = {Delayed {Heating} {Calculations} {Using} the {MCNP}-{ORIGEN} {Activation} {Automation} {Tool}},
	volume = {0},
	issn = {0029-5450},
	url = {https://doi.org/10.1080/00295450.2024.2319922},
	doi = {10.1080/00295450.2024.2319922},
	abstract = {An accurate assessment of the deposited energy across a reactor geometry allows for a better determination of the heat removal requirements and ensures effective cooling after shutdown. This work discusses several methods in detail that target the heat deposition in specific reactor regions, leading to a choice of a prevalent method for the calculation workflow. This paper introduces a delayed heating calculation workflow based on the formal three-step process. The workflow relies on the MCNP-ORIGEN Activation Automation tool for performing the first two steps of the process, while the third step is conducted via MCNP photon transport simulations. This paper showcases two applications to demonstrate the workflow and simulation outputs. These include an Advanced Test Reactor (ATR) experiment and the RA-6 reactor structures.},
	number = {0},
	urldate = {2024-06-03},
	journal = {Nuclear Technology},
	author = {Fairhurst-Agosta, Roberto E. and Kozlowski, Tomasz},
	year = {2024},
	note = {Publisher: Taylor \& Francis
\_eprint: https://doi.org/10.1080/00295450.2024.2319922},
	keywords = {ATR, Delayed heating, MCNP, ORIGEN, RA-6},
	pages = {1--13},
	file = {Full Text PDF:/Users/huff/Zotero/storage/ASCX66DP/Fairhurst-Agosta and Kozlowski - 2024 - Delayed Heating Calculations Using the MCNP-ORIGEN.pdf:application/pdf},
}

@article{lindsay_automatic_2021,
	title = {Automatic {Differentiation} in {MetaPhysicL} and {Its} {Applications} in {MOOSE}},
	copyright = {This material is published by permission of the Idaho National Laboratory, operated by Battelle Energy Alliance, for the U.S. Department of Energy under Contract No. DE-AC07-05ID14517. The U.S. Government retains for itself, and others acting on its behalf, a paid-up, non-exclusive, and irrevocable worldwide license in said article to reproduce, prepare derivative works, distribute copies to the public, and perform publicly and display publicly, by or on behalf of the Government.},
	issn = {0029-5450},
	url = {https://ans.tandfonline.com/doi/abs/10.1080/00295450.2020.1838877},
	abstract = {Efficient solution via Newton{\textquoteright}s method of nonlinear systems of equations requires an accurate representation of the Jacobian, corresponding to the derivatives of the component residual equations wi...},
	language = {EN},
	urldate = {2024-06-03},
	journal = {Nuclear Technology},
	author = {Lindsay, Alexander and Stogner, Roy and Gaston, Derek and Schwen, Daniel and Matthews, Christopher and Jiang, Wen and Aagesen, Larry K. and Carlsen, Robert and Kong, Fande and Slaughter, Andrew and Permann, Cody and Martineau, Richard},
	month = jul,
	year = {2021},
	note = {Publisher: Taylor \& Francis},
	file = {Snapshot:/Users/huff/Zotero/storage/NGHAGQ88/00295450.2020.html:text/html},
}

@phdthesis{bachmann_investigation_2023,
	type = {Thesis},
	title = {Investigation of the impacts of deploying reactors fueled by high-assay low enriched uranium},
	copyright = {Copyright by Amanda M. Bachmann. All rights reserved.},
	url = {https://hdl.handle.net/2142/121987},
	abstract = {The United States is considering the deployment of advanced reactors that require uranium enriched between 5-20\% 235U, often referred to as High Assay Low Enriched Uranium (HALEU). At the present, there are no commercial facilities in the US to produce HALEU, prompting questions of how to create a dependable supply chain of HALEU to support these reactors. HALEU can be produced through two primary methods: downblending High Enriched Uranium (HEU) and enriching natural uranium. The amount of HEU available and impurities present in the HEU limit downblending capabilities. The Separative Work Unit (SWU) capacity and amount of natural uranium available limit enriching natural uranium capabilities. To understand the resources necessary to commercially produce HALEU with each of these methods, one can quantify the material requirements of transitioning to HALEU-fueled reactors. 

In this dissertation, we model the transition from Light Water Reactors to different advanced reactors, considering once-through and closed fuel cycles to determine material requirements for supporting these fuel cycles. Material requirements of interest across this work include the mass of enriched uranium, mass of HALEU, feed uranium, SWU capacity, and the mass of used fuel sent for disposal. We use CYCLUS and publicly-available information about Light Water Reactors, the X-energy Xe-100, the Ultra Safe Nuclear Corporation Micro Modular Reactor, and the NuScale VOYGR to model potential transition scenarios and demonstrate the methodologies developed in this work. To more accurately model the closed fuel cycles, we develop a new CYCLUS archetype, called OpenMCyclus, that couples with OpenMC to dynamically model fuel depletion in a reactor and provide more accurate used fuel compositions. The results of this transition analysis show how the characteristics of the advanced reactors deployed drive the materials required to support the fuel cycle. Closing the fuel cycle reduces the materials required, but the reduction in materials is driven by the amount of material available for reprocessing. 

To gain more insight into how transition parameters not considered in the transition analysis affect material requirements, we perform sensitivity analysis on one of the once-through transitions by coupling CYCLUS with Dakota. The results of the sensitivity analysis highlight some of the trade-offs between different reactor designs. One such tradeoff is the increased HALEU demand but decreased used fuel discharged when increasing the Xe-100 deployment and decreasing the VOYGR deployment. Additionally, these results identify the Xe-100 discharge burnup as consistently being one of the most impactful input parameters for this transition, because of how the deployment scheme in this work affects the number of Xe-100s built no matter which advanced reactor build share is specified.

To identify potential transitions that minimize material requirements, we then use the CYCLUS-Dakota to optimize a once-through transition using the genetic algorithms in Dakota. In single-objective problems to minimize the SWU capacity required to produce HALEU and minimize the amount of used nuclear fuel, the algorithm finds solutions that are consistent with the results of the sensitivity analysis. The results cannot be taken at face value, because the algorithm did not fully converge and the genetic algorithms do not enforce the applied linear constraint for the advanced reactor build shares to sum to 100\%. However, the results provide guidance on how to adjust the input parameters to optimize the transition for a minimal HALEU SWU or the used fuel mass. Parameter adjustments include maximizing the number of Light Water Reactors that receive license extensions to operate for 80 years. Similar results occur when using this method for a multi-objective problem to minimize both the HALEU SWU capacity and the used fuel mass. 

Finally, we use neutronics models of the Xe-100 and Micro Modular Reactor reactor designs to evaluate the steady-state reactor physics performance of downblended HEU in these two designs. We compare the performance of the downblended HEU to nominally enriched fuel, based on the k-eff, $\beta$eff, energy- and spatially-dependent neutron fluxes, as well as the fuel, moderator, coolant, and total reactivity temperature feedback coefficients. The differences in the fuel compositions leads to differences in each of the metrics. However, these differences are within error of the results of the nominally enriched fuel, or would not prevent the reactor from meeting stated design specifications or operating in a safe state.

The work completed in this dissertation develops and demonstrates a methodology for modeling fuel cycle transitions and understanding the effects of deploying HALEU-fueled reactors in the US. The effects investigated in these example scenarios include various materials and resources required to support these reactors, and how the parameters of the transition affect these requirements. The information generated from this new methodology can be used to develop the necessary infrastructure and supply chains for support a transition to HALEU-fueled reactors. Furthermore, this work explores how the HALEU production method (enriching compared with downblending) affects reactor performance.},
	urldate = {2024-06-03},
	school = {University of Illinois at Urbana-Champaign},
	author = {Bachmann, Amanda M.},
	month = nov,
	year = {2023},
	file = {Full Text PDF:/Users/huff/Zotero/storage/K29LT23L/Bachmann - 2023 - Investigation of the impacts of deploying reactors.pdf:application/pdf},
}

@misc{noauthor_fuel_2023,
	address = {University of Illinois at Urbana-Champaign},
	title = {Fuel cycle needs of deploying advanced reactors},
	url = {https://github.com/abachma2/2023-04-19-tennessee/tree/main},
	abstract = {The US is looking to develop supplies of HALEU},
	month = apr,
	year = {2023},
}

@inproceedings{munk_preliminary_2012,
	title = {Preliminary design of a {FHR} test reactor core},
	volume = {106},
	language = {English},
	author = {Munk, M. and Cisneros, A.T. and Greenspan, E. and Peterson, P.F.},
	year = {2012},
	note = {ISSN: 0003-018X},
	pages = {834--835},
	file = {Snapshot:/Users/huff/Zotero/storage/2W3FCEVM/display.html:text/html},
}

@inproceedings{munk_design_2015,
	title = {Design and feasibility study of a compact neutron source for extraterrestrial geochronology applications},
	volume = {4},
	isbn = {978-1-5108-0804-1},
	abstract = {The 40Ar/39Ar radiometric dating technique is an attractive option for future extraterrestrial geochronology applications. However, in situ 40Ar/39Ar radiometric dating on Mars presents unique challenges to the design of a device capable of achieving sufficient precision on geological samples obtained on the Martian surface. For this application, a fast neutron source with a low thermal neutron flux is ideal for inducing the 39K(n,p)39Ar reaction with few competing reactions that require age-correction factors. This paper explores the design of a neutron emitting device specifically for in situ geochronological applications on extraterrestrial surfaces. We have determined that a feasible design is likely to include a 252Cf spontaneous fission source shielded by polyethylene layered with a strong thermal neutron absorber. Although boosting options-induced fission sources, ($\alpha$,n)-are available, they do not provide sufficient neutron multiplicity to justify the increased mass of the device. Furthermore, shielding the rover from the neutron source will likely comprise the largest fractional mass of the device, which will be reduced by shielding only a small solid angle of the source. While we have determined that it is possible to design such a neutron source, there will also be other instrumentation competing for a mass fraction of the Rover instrument payload. This may make it difficult to design a device that achieves the required mass and fluence limitations for a future mission. However, this work provides a realistic path forward in determining a future workable design. Copyright {\textcopyright} (2015) by the American Nuclear Society All rights reserved.},
	language = {English},
	author = {Munk, M. and Slaybaugh, R. and Van Bibber, K. and Morgan, L. and Davidheiser-Kroll, B. and Mark, D.},
	year = {2015},
	keywords = {Argon/Argon Geochronology, Fisson Sources, Mars},
	pages = {3125--3138},
	annote = {Cited By :1},
	file = {Snapshot:/Users/huff/Zotero/storage/MMWU83WK/display.html:text/html},
}

@inproceedings{munk_fwcadis-_2016,
	title = {{FW}/{CADIS}-$\Omega$: {An} angle-informed hybrid method for deep-penetration radiation transport},
	volume = {2},
	isbn = {978-1-5108-2573-4},
	shorttitle = {{FW}/{CADIS}-$\Omega$},
	abstract = {A new method for generating variance reduction parameters for strongly anisotropic, deep-penetration radiation shielding studies is presented. This method generates an alternate form of the adjoint scalar flux quantity, $\varphi${\textdagger}$\Omega$ which is used by both CADIS and FW-CADIS to generate variance reduction parameters for local and global response functions, respectively. The new method, called CADIS-$\Omega$, was implemented in the Denovo/ADVANTG software suite, and results are presented for a concrete labyrinth test problem. Results indicate that the flux generated by CADIS-$\Omega$ incorporates localized angular anisotropics in the flux effectively. CADIS-$\Omega$ outperformed CADIS in the test problem while obtaining correct results. This initial work indicates that CADIS-$\Omega$ may be highly useful for shielding problems with strong angular anisotropics. A future test plan to fully characterize the new method is proposed, which should reveal more about the types of realistic problems for which the CADIS-$\Omega$ will be suited.},
	language = {English},
	author = {Munk, M. and Slaybaugh, R.N. and Pandya, T.M. and Johnson, S.R. and Evans, T.M.},
	year = {2016},
	keywords = {Angular Biasing, CADIS, FW-CADIS, Hybrid Methods},
	pages = {1069--1086},
	annote = {Cited By :1},
	file = {Snapshot:/Users/huff/Zotero/storage/A2DYDM3F/display.html:text/html},
}

@article{morgan_instrumentation_2017,
	title = {Instrumentation {Development} for {In} {Situ} {40Ar}/{39Ar} {Planetary} {Geochronology}},
	volume = {41},
	copyright = {{\textcopyright} 2017 The Authors. Geostandards and Geoanalytical Research published by John Wiley \& Sons Ltd on behalf of International Association of Geoanalysts.},
	issn = {1751-908X},
	url = {https://onlinelibrary.wiley.com/doi/abs/10.1111/ggr.12170},
	doi = {10.1111/ggr.12170},
	abstract = {The chronology of the Solar System, particularly the timing of formation of extra-terrestrial bodies and their features, is an outstanding problem in planetary science. Although various chronological methods for in situ geochronology have been proposed (e.g., Rb-Sr, K-Ar), and even applied (K-Ar), the reliability, accuracy, and applicability of the 40Ar/39Ar method makes it by far the most desirable chronometer for dating extra-terrestrial bodies. The method however relies on the neutron irradiation of samples, and thus a neutron source. Herein, we discuss the challenges and feasibility of deploying a passive neutron source to planetary surfaces for the in situ application of the 40Ar/39Ar chronometer. Requirements in generating and shielding neutrons, as well as analysing samples are described, along with an exploration of limitations such as mass, power and cost. Two potential solutions for the in situ extra-terrestrial deployment of the 40Ar/39Ar method are presented. Although this represents a challenging task, developing the technology to apply the 40Ar/39Ar method on planetary surfaces would represent a major advance towards constraining the timescale of solar system formation and evolution.},
	language = {en},
	number = {3},
	urldate = {2024-06-03},
	journal = {Geostandards and Geoanalytical Research},
	author = {Morgan, Leah E. and Munk, Madicken and Davidheiser-Kroll, Brett and Warner, Nicholas H. and Gupta, Sanjeev and Slaybaugh, Rachel and Harkness, Patrick and Mark, Darren F.},
	year = {2017},
	note = {\_eprint: https://onlinelibrary.wiley.com/doi/pdf/10.1111/ggr.12170},
	keywords = {Ar-Ar dating, geochronology, instrumentation, mass spectrometry, neutron source},
	pages = {381--396},
	file = {Full Text:/Users/huff/Zotero/storage/8VDQMTKA/Morgan et al. - 2017 - Instrumentation Development for In Situ 40Ar39Ar .pdf:application/pdf;Snapshot:/Users/huff/Zotero/storage/9X5PPS35/ggr.html:text/html},
}

@article{havlin_3d_2021,
	title = {{3D} volume rendering of geophysical data using the yt platform},
	url = {https://essopenarchive.org/doi/full/10.1002/essoar.10506118.2},
	doi = {10.1002/essoar.10506118.2},
	abstract = {We present novel applications of yt, a tool originally designed for analysis of astrophysics datasets, to the geosciences. yt is a python-based platform for volumetric data, which enables semantically meaningful analysis and visualization. As part of a wider effort to bring yt to the geosciences, we present an initial use-case of yt applied to 3D seismic tomography models of the upper mantle from the IRIS Earth Model Collaboration. While the rendering capabilities of yt can in general be applied directly to 3D geoscience data, we add several graphical elements to the 3D rendering to aid in interpretation of volume renderings including latitude/longitude overlays and shapefile suport for plotting political and tectonic boundaries along the Earth{\textquoteright}s surface. In this notebook, we focus on tomographic models of North America and the Western U.S., where high resolution models and rapidly varying seismic properties provide a rich dataset to explore systematically at a range of lengthscales. The notebook demonstrates loading and rendering of IRIS netcdf models, highlighting interesting 3D features of the Western U.S. upper mantle, and goes on to demonstrate how having direct control of the transfer functions used in creating the final volume rendering allows for a more systematic exploration of the role of the visualization method in our interpretation of 3D volumetric data. Finally, we conclude by demonstrating some of the semantically-aware capabilities of yt for analysis purposes, and demonstrate how these tools have cross-disciplinary functionality.},
	language = {en},
	urldate = {2024-06-03},
	journal = {Earth and Space Science Open Archive},
	author = {Havlin, Christopher and Holtzman, Benjamin and Kowalik, Kacper and Munk, Madicken and Walkow, Samantha and Turk, Matthew},
	month = feb,
	year = {2021},
	doi = {10.1002/essoar.10506118.2},
}

@article{munk_widgyts_2020,
	title = {widgyts: {Custom} {Jupyter} {Widgets} for {Interactive} {Data} {Exploration} with yt},
	volume = {5},
	issn = {2475-9066},
	shorttitle = {widgyts},
	url = {https://joss.theoj.org/papers/10.21105/joss.01774},
	doi = {10.21105/joss.01774},
	abstract = {Munk et al., (2020). widgyts: Custom Jupyter Widgets for Interactive Data Exploration with yt. Journal of Open Source Software, 5(45), 1774, https://doi.org/10.21105/joss.01774},
	language = {en},
	number = {45},
	urldate = {2024-06-03},
	journal = {Journal of Open Source Software},
	author = {Munk, Madicken and Turk, Matthew J.},
	month = jan,
	year = {2020},
	pages = {1774},
	file = {Full Text PDF:/Users/huff/Zotero/storage/B8MKULDB/Munk and Turk - 2020 - widgyts Custom Jupyter Widgets for Interactive Da.pdf:application/pdf},
}

@article{lindsay_coupling_2016,
	title = {Coupling of {Plasmas} and {Liquids}.},
	url = {http://www.lib.ncsu.edu/resolver/1840.16/11273},
	abstract = {LINDSAY, ALEXANDER DAVID. Coupling of Plasmas and Liquids. (Under the direction of
Steven Shannon.)
Plasma-liquids have exciting applications to several important socioeconomic areas, including
agriculture, water treatment, and medicine. To realize their application potential, the basic
physical and chemical phenomena of plasma-liquid systems must be better understood. Additionally, system designs must be optimized in order to maximize fluxes of critical plasma species
to the liquid phase. With objectives to increase understanding of these systems and optimize
their applications, we have performed both comprehensive modelling and experimental work. To
date, models of plasma-liquids have focused on configurations where diffusion is the dominant
transport process in both gas and liquid phases. However, convection plays a key role in many
popular plasma source designs, including jets, corona discharges, and torches. In this dissertation,
we model momentum, heat, and neutral species mass transfer in a convection-dominated system
based on a corona discharge. We show that evaporative cooling produced by gas-phase convection
can lead to a significant difference between gas and liquid phase bulk temperatures. Additionally,
convection induced in the liquid phase by the gas phase flow substantially increases interfacial
mass transfer of hydrophobic species like NO and NO2. Finally, liquid kinetic modelling suggests that concentrations of highly reactive species like OH and ONOOH are several orders of
magnitude higher at the interface than in the solution bulk.
Subsequent modelling has focused on coupling discharge physics with species transport at and
through the interface. An assumption commonly seen in the literature is that interfacial loss
coefficients of charged species like electrons are equal to unity. However, there is no experimental
evidence to either deny or support this assumption. Without knowing the true interfacial behavior
of electrons, we have explored the effects on key plasma-liquid variables of varying interfacial
parameters like the electron and energy surface loss coefficients. Within a reasonable range for
these parameters, we have demonstrated that the electron density on the gas phase side of the
interface can vary by orders of magnitude. Significant effects can also be seen on the gas phase
interfacial electron energy. Electron density and energy will play important roles in determining
gas phase chemistry in more complex future models; this will in turn feed back into the liquid
phase chemistry. To remove this uncertainty in interfacial behavior, we recommend finer scale
atomistic or molecular dynamics simulations. Efficient coupling of the highly non-linear discharge
physics equations to liquid transport required creation of a new simulation code named Zapdos,
built on top of the MOOSE framework. The operation and capabilities of the code are described
in this work. Moreover, changes made to the MOOSE framework allowing coupling of physics
across subdomain boundaries, necessary for plasma-liquid coupling, are also detailed.
In the latter half of this work, we investigate experimental optimization and characterization of
plasma-liquid interactions surrounding a unique very high frequency (VHF) plasma discharge.
Several geometric configurations are considered. In the most promising set-up, the discharge
is pointed upwards and water is pumped through the source{\textquoteright}s inner conductor until it forms
a milimeter thick water layer on top of the powered electrode. This maximizes the amount of
charged and neutral species flux received by the aqueous phase as well as the amount of water
vapor created in the gas phase. Additionally, the configuration eliminates electrode damage by
providing an infinitely renewable liquid surface layer. The presence of large amounts of water
vapor and OH radicals is confirmed by optical emission and broadband absorption spectroscopy.
Characterization of liquid phase species like NO-
3
, NO-
2
, and H2O2 is carried out through ion
chromatography (IC) and colorimetric measurements.
After detailing the design and characterization of our plasma-liquid systems, we illustrate their
applications to plant fertilization and wastewater disinfection. In a four-week collaborative experiment with the NCSU greenhouse, plants that received plasma-treated water grew significantly
larger than plants that received tap water. This is directly attributable to the approximately
hundred mg/L of NO-
3 dissolved into solution by the plasma. The VHF source also proved
effective at removing several aqueous contaminants designated harmful to humans by the EPA.
Air plasma treatment of solutions contaminated with 1,4-dioxane showed log reduction times
competitive with other advanced oxidative processes (AOP). Argon treatment of dixoane was an
order of magnitude more effective in terms of log reduction time, although the associated costs
are significantly higher. Perfluorooctanesulfonic acid (PFOS) proved resistant to several VHF
design iterations. However, the water electrode design introduced in the passage above achieved a
log reduction in low level PFOS concentrations over the course of twenty five minutes, suggesting
that it may be viable as an advanced technology for degradation of persistent perfluorinated
compounds.
Future work will serve to further unify the modelling and experimental work presented here.
Three dimensional models are being actively developed to explore the spreading of discharges
over water as a function of the water conductivity. Electromagnetic models are also being
introduced into Zapdos that will enable simulation of the VHF source in contact with liquids.
Completion of those models will be followed by simulations attempting to reproduce the gaseous
OH density and liquid phase NO-
x and H2O2 concentration measurements.},
	language = {en},
	urldate = {2024-06-04},
	author = {Lindsay, Alexander David},
	month = apr,
	year = {2016},
	note = {Dissertation},
	file = {Full Text PDF:/Users/huff/Zotero/storage/8WBUD7GD/Lindsay - 2016 - Coupling of Plasmas and Liquids..pdf:application/pdf},
}

@techreport{schwen_bison_2019,
	title = {Bison {Robustness} and {Performance} {Improvements}},
	url = {https://www.osti.gov/biblio/1530814},
	abstract = {In last year{\textquoteright}s Bison robustness report, the authors demonstrated that improving the Jacobian matrix can drastically increase solution convergence rates. The development of an automatic differentiation (AD) capability in the MOOSE framework has created the possibility of having exact Jacobian matrices for all of our material models. A large focus in this year{\textquoteright}s report is the application of AD to MOOSE physics modules, such as the tensor mechanics module, and the application to Bison fuel and cladding material models. A second main focus in this year{\textquoteright}s report is the investigation of a set of algorithmic solver changes to improve the robustness and performance of Bison LWR simulations. Beyond providing increased solver robustness, the ability to solve strongly coupled multiphysics problems, and solving large deformation problems with ease, these automatically generated perfect Jacobians also drastically reduce development time for new models. In models converted to AD, Jacobian computation made up the majority of the code base. With this code removed, both readability and maintainability of the MOOSE/Bison code base are improved. The work documented here significantly improved the robustness of the Bison LWR assessment case suite. Through algorithmic changes in solver infrastructure, such as the application of predictors and improvements in timestepping, tangible improvements in performance were observed. These improvements are documented using a new standard set of metrics that are collected in all assessment cases, and a suite of statistical analysis tools developed for this report.},
	language = {English},
	number = {INL/EXT-19-54481-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Schwen, Daniel and Spencer, Benjamin W. and Pitts, Stephanie A. and McDowell, Dylan James and Stafford, Shane},
	month = jun,
	year = {2019},
	doi = {10.2172/1530814},
	file = {Full Text PDF:/Users/huff/Zotero/storage/VCABR5IH/Schwen et al. - 2019 - Bison Robustness and Performance Improvements.pdf:application/pdf},
}

@techreport{terlizzi_nrc_2021,
	title = {{NRC} {Multiphysics} {Analysis} {Capability} {Deployment} {FY21}: {Part} 3},
	shorttitle = {{NRC} {Multiphysics} {Analysis} {Capability} {Deployment} {FY21}},
	url = {https://www.osti.gov/biblio/2322530},
	abstract = {This report details the progress and activities of Idaho National Laboratory (INL) on the Nuclear Regulatory Commission (NRC) project {\textquotedblleft}Development and Modeling Support for Advanced Non-Light Water Reactors.{\textquotedblright} The deliverables completed for this report are: Deliverable 1c: the capability to model gas mixtures was added to Pronghorn. A test problem mimicking the conditions achieved in a depressurized loss of forced cooling (DLOFC) event was solved with both RELAP-5 and Pronghorn. Pronghorn employed a finite vol ume method with the Kurganov-Tadmor discretization. The comparison between the mass fraction spatial profiles computed with RELAP-5 and Pronghorn clearly shows the presence of numerical artifacts (i.e., overly diffusive behavior at low Mach numbers). We confirmed that the problem disappears at higher Mach numbers. We recommend future work on the implementation of a low Mach finite volume formulation to better treat low Mach number problems. Deliverable 2a: we demonstrated two approaches to model the radiation/conduction/natural convection heat transfer across a stagnant gas for the PBMR-400 design using Pronghorn. The first approach is based on the net radiation method, which relies on the computation of view factors with the Multiphysics Object-Oriented Simulation Environment (MOOSE) ray tracing capability. The second method is a traditional thermal resistance approach. The test problems include both 2D and 3D geometries. In all cases, the results show very good agreement during a DLOFC transient. This confirms that the faster thermal resistance method produces solutions that are equivalent to the net radiation method for this geometry. Deliverable 3d: we demonstrated the use of the advection kernel for the delayed neutron precursor equation in Griffin with a 2D MSFR model. The results appear physical but further verification is recommended. We also recommend the addition of conjugate heat transfer to compute the temperatures and model the thermomechanic behavior of the reflectors and other structures. Significant memory and performance issues were encountered in the 3D axisymmetric model. Future work is recommended in this area. Task 8g: this task allows multidimensional MOOSE applications to be coupled to system codes (RELAP-7 and SAM). We implemented a faster multiphysics iteration coupling algorithm, which provides an overall 6{\texttimes} acceleration of the 3D-1D coupling of the core multidi- mensional fluid flow solver and the 1D primary and secondary loop model.},
	language = {English},
	number = {INL/EXT-21-63429-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Terlizzi, Stefano and Giudicelli, Guillaume Louis and Balestra, Paolo and Lindsay, Alexander D. and Ortensi, Javier and Mueller, Cole Michael},
	month = jul,
	year = {2021},
	doi = {10.2172/2322530},
	file = {Full Text PDF:/Users/huff/Zotero/storage/5E4UTARV/Terlizzi et al. - 2021 - NRC Multiphysics Analysis Capability Deployment FY.pdf:application/pdf},
}

@techreport{lindsay_useability_2022,
	title = {Useability and {Optimization} {Improvements} in {MOOSE}},
	url = {https://www.osti.gov/biblio/1985999},
	abstract = {The Multiphysics Object-Oriented Simulation Environment (MOOSE) framework is a foundational capability used by the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program to create over 15 different simulation tools for advanced nuclear reactors. Due to this broad use, improvements to the framework in support of modeling and simulation goals are critical to the program. These improvements can take many forms, including optimization, improved user experience, streamlined application programming interfaces (APIs), parallelism, and new capabilities. The work transcribed in this report was conducted in direct support of the simulation tools and has already been deployed or will be deployed in the coming months. The capabilities were implemented in the same order as they are covered in this report: increased support of face variables, arbitrary spatial and temporal evaluation of material properties, and the addition of a triangular meshing library in libMesh.},
	language = {English},
	number = {INL/RPT-22-69413-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Lindsay, Alexander D. and Gaston, Derek R. and Permann, Cody J. and Giudicelli, Guillaume Louis and Stogner, Roy Hulen},
	month = sep,
	year = {2022},
	doi = {10.2172/1985999},
	file = {Full Text PDF:/Users/huff/Zotero/storage/8SEV5R7G/Lindsay et al. - 2022 - Useability and Optimization Improvements in MOOSE.pdf:application/pdf},
}

@incollection{pitts_chapter_2024,
	title = {Chapter 14 - {Modeling} and simulation of advanced manufacturing techniques using {MOOSE} and {MALAMUTE}},
	isbn = {978-0-323-91152-8},
	url = {https://www.sciencedirect.com/science/article/pii/B9780323911528000090},
	abstract = {Advanced manufacturing techniques offer increased geometry complexity, energy and material usage efficiency improvements, and an expanded palette of materials as compared to conventional manufacturing approaches. Advanced manufacturing (AM)-produced parts can experience wide variations in the final microstructure, and these microstructure variations significantly impact the parts{\textquoteright} performance. In this chapter, we present recent code developments within the Multiphysics Object-Oriented Simulation Environment (MOOSE) and in the MOOSE Application Library for Advanced Manufacturing UTilitiEs (MALAMUTE). Here we demonstrate applying these modeling and simulation codes to two advanced manufacturing process types: advanced sintering techniques and laser-based additive manufacturing techniques. The multiphysics and multiscale capabilities of these codes enable the prediction of the microstructure evolution resulting from variations in the advanced manufacturing process parameters.},
	urldate = {2024-06-04},
	booktitle = {Risk-{Informed} {Methods} and {Applications} in {Nuclear} and {Energy} {Engineering}},
	publisher = {Academic Press},
	author = {Pitts, Stephanie A. and Biswas, Sudipta and Yushu, Dewen and Lindsay, Alexander D. and Jiang, Wen and Aagesen, Larry K.},
	editor = {Smith, Curtis Lee and Le Blanc, Katya and Mandelli, Diego},
	month = jan,
	year = {2024},
	doi = {10.1016/B978-0-323-91152-8.00009-0},
	keywords = {Advanced manufacturing simulation, Direct-energy deposition, MALAMUTE, Microstructure, MOOSE, Multiphysics simulation, Multiscale simulation, Powder-bed fusion, Sintering},
	pages = {263--286},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/R827B8VD/B9780323911528000090.html:text/html},
}

@inproceedings{icenhour_electromagnetics_2019,
	address = {Spokane, Washington, USA},
	title = {Electromagnetics {Simulations} with {Vector}-valued {Finite} {Elements} in {MOOSE}},
	url = {https://www.osti.gov/biblio/1503606},
	abstract = {Vector-valued finite elements have become an essential part of modern electromagnetic (EM) numerical simulation. This talk will describe the development and initial validation of a MOOSE-based EM solver application, ELK (Electromagnetics Library for Kinetics and fluids), that utilizes the recently added vector-valued finite element system. The primary motivation for the development of ELK was to study EM wave propagation in radio-frequency (rf) driven systems, such as those encountered in the study of antenna structures, waveguides, and plasma physics. In simulating these scenarios with traditional scalar-valued finite elements, boundary conditions on tangential field components can sometimes be difficult to define, and field discontinuities encountered with certain geometric or structural features (e.g., abrupt corners and inhomogeneous materials) can often lead to non-physical results. Vector-valued elements can largely mitigate and even eliminate these difficulties. ELK verification and validation efforts thus far have focused on standard wave propagation benchmarks for antennas and waveguides, and the impact of vector-valued elements on the implementation and results of these simulations will be described. Progress using ELK for plasma physics simulation, where inhomogeneous simulation domains are commonplace, will also be discussed.},
	language = {English},
	urldate = {2024-06-04},
	booktitle = {2019 {SIAM} {Conference} on {Computational} {Science} and {Engineering}},
	publisher = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Icenhour, Casey T. and Lindsay, Alexander D. and Martineau, Richard C. and Shannon, Steven},
	month = feb,
	year = {2019},
	note = {Report Number: INL/CON-18-52320-Rev000},
	file = {Full Text PDF:/Users/huff/Zotero/storage/9EMZZ6AI/Icenhour et al. - 2019 - Electromagnetics Simulations with Vector-valued Fi.pdf:application/pdf},
}

@techreport{schunert_finite_2020,
	title = {Finite {Volume} {Discretization} of the {Euler} {Equations} in {Pronghorn}},
	url = {https://www.osti.gov/biblio/1907648},
	abstract = {Modeling flow and heat transfer in high temperature gas reactors (HTGR) requires the ability to model a wide range of flow speeds from slow (natural convection), to intermediate (forced-flow conditions), to supersonic regimes (depressurization) for a wide range of geometries including the pebble bed, upper and lower plenum, and risers. In previous work, Pronghorn has effectively modeled low-to-medium speed flows in scenarios such as the one described in the two-dimensional PBMR-400 benchmark, using its finite-element-based streamline-upwind Petrov-Galerkin (SUPG) stabilized implementation of the Euler equations. However, limitations of this method become apparent when dealing with more complicated geometries (e.g. imposing slip boundary conditions at nodes belonging to two different boundaries) and when gas speeds are fast enough for shocks and supersonic flow to occur. For these problems, the finite-element-based solver lacks robustness and is plagued by slow iterative convergence or even divergence. In order to address these challenges, the Pronghorn code at INL has been updated with new, modified versions of its original equations. The new Pronghorn models are built on the finite volume method with a Harten-Lax-van Leer-Contact (HLLC) Riemann solver based numerical flux method, which (1) allows imposing slip boundary conditions much more robustly and (2) performs well for a wide range of flow speeds. The finite-volume-based flow solver will form the basis for a robust coarse-mesh thermal-hydraulics capability in Pronghorn.},
	language = {English},
	number = {INL/EXT-20-58883-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Schunert, Sebastian and Carlsen, Robert W. and MacDonald, Nolan Eric and Hansel, Joshua E. and Lindsay, Alexander D.},
	month = jun,
	year = {2020},
	doi = {10.2172/1907648},
	file = {Full Text PDF:/Users/huff/Zotero/storage/MTSI96W3/Schunert et al. - 2020 - Finite Volume Discretization of the Euler Equation.pdf:application/pdf},
}

@inproceedings{byrns_plasma_2013,
	title = {Plasma assisted water treatment using an atmospheric air plasma applicator},
	url = {https://ieeexplore.ieee.org/abstract/document/6635082},
	doi = {10.1109/PLASMA.2013.6635082},
	abstract = {Plasma assisted water treatment systems present a compelling pathway for modification of water chemistry with reduced dependence on chemicals. Plasma production of oxidizing and reducing agents for chemical abatement, contaminant removal, and production of aqueous chemical agents without chemical feedstock present a potential transformative technology in the area of water treatment.An atmospheric plasma source operating at 162MHz1 is used to form reactive species that are incident on a downstream water source. While studying a variety of water treatment applications, several key challenges for practical implementation of this technology have been identified including improved pathways for water/plasma interaction and optimized chemistry for specific water treatment applications. Design of an improved device with increased efficiency in both airflow and water exposure will be presented. The interaction between the primary plasma discharge and water source, with emphasis on chemical composition and potential pathways for chemistry control are highlighted. Of specific interest is production and characterization of hydroxyl radicals through plasma water interaction. Experiments that characterize plasma conditions (specifically chemistry) andchanges to water chemistry will be presented. Potential applications of interest in the area of water treatment including treatment of perfluorinated compounds, atrazine, and dioxane in water supplies will be presented.},
	urldate = {2024-06-04},
	booktitle = {2013 {Abstracts} {IEEE} {International} {Conference} on {Plasma} {Science} ({ICOPS})},
	author = {Byrns, Brandon and Lindsay, Alex and Knappe, Detlef and Shannon, Steven},
	month = jun,
	year = {2013},
	note = {ISSN: 0730-9244},
	keywords = {Chemicals, Educational institutions, Plasma sources, Production, Water resources},
	pages = {1--1},
	file = {IEEE Xplore Abstract Record:/Users/huff/Zotero/storage/NBSRZIZI/6635082.html:text/html;IEEE Xplore Full Text PDF:/Users/huff/Zotero/storage/FXYM3QI8/Byrns et al. - 2013 - Plasma assisted water treatment using an atmospher.pdf:application/pdf},
}

@misc{hansel_idaholabnitrogen_2024,
	title = {idaholab/nitrogen},
	copyright = {LGPL-2.1},
	url = {https://github.com/idaholab/nitrogen},
	urldate = {2024-06-04},
	publisher = {Idaho National Laboratory},
	author = {Hansel, Joshua and Lindsay, Alexander},
	month = jun,
	year = {2024},
	note = {original-date: 2023-06-14T22:38:38Z},
}

@article{noauthor_nitroflow_2024,
	title = {{NitroFlow}: {Dynamic} {Nitrogen} {Properties} {Simulation} {Tool}},
	shorttitle = {{NitroFlow}},
	abstract = {NitroFlow is a versatile software library designed to compute a myriad of nitrogen properties using the interfaces of the MOOSE fluid properties module. The software is beneficial in its ability to compute thermodynamic properties, including temperature, pressure, and density, as well as transport properties like thermal conductivity and dynamic viscosity. This is accomplished based on two independent, intensive thermodynamic properties. The software can integrate with the MOOSE finite element framework or other MOOSE-based applications, allowing for enhanced fluid simulations. Its primary audience comprises researchers and analysts across diverse engineering disciplines involving fluid flow, who can leverage this tool for precise, comprehensive fluid property analysis.This software is open source and available at no cost.},
	journal = {Advanced Scientific Computing},
	year = {2024},
}

@techreport{lindsay_neams-multiphysics_2024,
	title = {{NEAMS}-{Multiphysics} {MOOSE} {End} {Year} {Framework} {Activities} {FY20}},
	url = {https://www.osti.gov/biblio/2305671},
	abstract = {The Multiphysics Object Oriented Simulation Environment (MOOSE) is a general finite element package meant for high performance solution of multiphysics problems in science and engineering. In this report, we present additions and enhancements to MOOSE funded by the Nuclear Engineering Advanced Modeling and Simulation (NEAMS) program. NEAMS-funded MOOSE framework library improvements include: expansion of support for multi-level multi-application restart; enhancement of coupling between native MOOSE applications and external libraries; addition of a sparse automatic differentiation (AD) container enabling non-local degree of freedom coupling; block-specific quadrature rules; further development of an eigenvalue executioner; faster setup of periodic boundary conditions; and creation of a mesh meta-data system streamlining simulation startup. Besides developing the framework library, NEAMS funds were used to overhaul a swath of important MOOSE infrastructure in order to substantially improve user experience. These critical infrastructure changes included adapting MOOSE to python 3, improving the test harness to catch race conditions, and most importantly transitioning MOOSE to use Conda, a globally known packaging system, that greatly eases software adoption.},
	language = {English},
	number = {INL/EXT-20-59837-Rev000; INL/EXT-20-59837},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Lindsay, Alexander D. and Kong, Fande and Carlsen, Robert W. and Miller, Jason Mathew and Slaughter, Andrew E. and Stogner, Roy and Permann, Cody J. and Gaston, Derek R.},
	month = feb,
	year = {2024},
	doi = {10.2172/2305671},
	file = {Full Text PDF:/Users/huff/Zotero/storage/K9W5SZH8/Lindsay et al. - 2024 - NEAMS-Multiphysics MOOSE End Year Framework Activi.pdf:application/pdf},
}

@inproceedings{lindsay_cross-cutting_2024,
	address = {Chicago},
	title = {Cross-{Cutting} {Capability} in {MOOSE} for {Advanced} {Reactor} {Simulation}},
	url = {https://www.osti.gov/biblio/2299544},
	abstract = {This presentation highlights NEAMS multiphysics work conducted by the MOOSE team in fiscal year 2022.},
	language = {English},
	urldate = {2024-06-04},
	booktitle = {{NEAMS} {Annual} {Review}},
	publisher = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Lindsay, Alexander D. and Giudicelli, Guillaume Louis and Stogner, Roy Hulen},
	month = feb,
	year = {2024},
	note = {Report Number: INL/CON-22-69936-Rev000},
	file = {Full Text PDF:/Users/huff/Zotero/storage/XM2IVK5K/Lindsay et al. - 2024 - Cross-Cutting Capability in MOOSE for Advanced Rea.pdf:application/pdf},
}

@article{recuero_multidimensional_2024,
	title = {Multidimensional modeling of fuel-cladding friction in an {LWR} fuel rod},
	volume = {424},
	issn = {0029-5493},
	url = {https://www.sciencedirect.com/science/article/pii/S0029549324003911},
	doi = {10.1016/j.nucengdes.2024.113291},
	abstract = {Solving finite element problems with friction often increases the level of difficulty to obtain properly converged solutions. This type of challenge becomes more salient when advanced, possibly multiscale, material models are employed to capture the thermomechanical behavior of fuel and cladding materials. The present work details our recent developments in a nuclear fuel performance finite element code for the systematic consideration of friction in nuclear reactor finite element simulations. We show the application of friction and its effects on the mechanics of light-water reactor rods accounting for various fuel constitutive modeling techniques, model dimensionalities, pellet assumed geometries, and power conditions. In particular, we focus on the fuel rod mechanical behavior as it relates to fuel constitutive models, sensitivity to the coefficient of friction, pellet states of stress, and rod elongation. We discuss the trade-offs between the various multidimensional modeling options and highlight the relevance of frictional effects in the prediction of the fuel rod deformation and interfacial stresses. To relate our modeling results with actual reactor operation, simulations including frictional effects are compared with fuel rod elongation experimental data and some challenges for carrying out a full validation of the axial mechanics are discussed.},
	urldate = {2024-06-04},
	journal = {Nuclear Engineering and Design},
	author = {Recuero, A. M. and Gamble, K. A. and Yushu, D. and Lindsay, A. D.},
	month = aug,
	year = {2024},
	keywords = {BISON, Contact mechanics, Friction, Fuel performance, Pellet-cladding mechanical interaction},
	pages = {113291},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/UYZ6IPX2/S0029549324003911.html:text/html},
}

@inproceedings{wang_optimization_2019,
	address = {Washington, D.C.},
	title = {Optimization of the rattlesnake code with array variables/kernels: 2019 {Transactions} of the {American} {Nuclear} {Society}, {ANS} 2019},
	volume = {121},
	shorttitle = {Optimization of the rattlesnake code with array variables/kernels},
	url = {http://www.scopus.com/inward/record.url?scp=85092200714&partnerID=8YFLogxK},
	doi = {10.13182/T31235},
	urldate = {2024-06-04},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	author = {Wang, Yaqi and Gaston, Derek and Lindsay, Alexander and Laboure, Vincent},
	month = nov,
	year = {2019},
	pages = {773--776},
	annote = {Funding Information:This manuscript has been authored by Battelle Energy Alliance, LLC under Contract No. DE-AC07-05ID14517 with the U.S. Department of Energy. The United States Government retains and the publisher, by accepting the article for publication, acknowledges that the United States Government retains a nonexclusive, paid-up, irrevocable, world-wide license to publish or reproduce the published form of this manuscript, or allow others to do so, for United States Government purposes. The authors thank the Rattlesnake and MOOSE development team for helpful comments and feedbacks.},
}

@inproceedings{okyay_validation_2023,
	address = {Washington D.C.},
	title = {Validation and {Comparison} of {HI}-{STORM} {Overpack} {Thermal}-{Hydraulic} {Model} with {MOOSE} and {NekRS}},
	url = {https://www.ans.org/pubs/proceedings/article-54158/},
	abstract = {Nuclear power is a significant source of electricity in the United States, but the average U.S. nuclear power plant is
around 40 years old. Safe management of spent nuclear fuel (SNF) is a crucial aspect of the back end of the nuclear
fuel cycle. SNF dry storage systems are increasingly popular as they represent an effective solution in this area, given
the absence of a final disposal system. In particular, the spent fuel cask system (dry cask method) provides a feasible
solution for maintaining SNF (\~{}60 years) prior to the final disposal.
The HI-STORM overpack and MPC-32 canister are the primary components of the HI-STORM 100 dry cask storage system. They remove heat from the system via natural circulation with no human intervention required. This
characteristic provides passive heat removal while requiring little maintenance in dry cask storage systems.
This project aims to validate and compare the capabilities of a thermal model of HI-STORM overpack developed using
the Multiphysics Object-Oriented Simulation Environment (MOOSE) based on the author{\textquoteright}s previous study. MOOSE
is an open-source framework developed by Idaho National Laboratory for multiscale, multiphysics simulations. This
study will improve the capabilities of the thermal-hydraulic model of the HI-STORM dry cask storage system by producing high-fidelity results for the air circulation in the overpack. Large Eddy Simulations (LES) are performed using
the open-source spectral element code NekRS, developed by Argonne National Laboratory (ANL), for simulating
transitional and turbulent flows in complex geometries. NekRS will produce high-fidelity results for the HI-STORM
overpack to assess the validity of the current thermal-hydraulic model.
This work aims to improve the modeling of the HI-STORM overpack system that was previously developed and
validated. The objective of obtaining high-fidelity results is to gain a deeper understanding of the turbulence characteristics of air circulation in the HI-STORM overpack systems, which will then be used to validate the assumptions
of lower-fidelity models. Finally, the results produced by NekRS will be compared with those of the current MOOSE
model to evaluate the performance of both models.},
	urldate = {2024-06-04},
	booktitle = {20th {International} {Topical} {Meeting} on {Nuclear} {Reactor} {Thermal} {Hydraulics} ({NURETH}-20)},
	author = {Okyay, Sinan and Merzari, Elia and Reger, David A. and Leite, Victor Coppo and Giudicelli, Guillaume and German, Peter and Lindsay, Alexander},
	month = aug,
	year = {2023},
	file = {Proceedings -- ANS / Publications / Proceedings:/Users/huff/Zotero/storage/Q9J98LF9/article-54158.html:text/html},
}

@article{recuero_approach_2023,
	title = {An approach to grid-to-rod fretting wear modeling using dynamic mortar contact},
	volume = {163},
	issn = {0149-1970},
	url = {https://www.sciencedirect.com/science/article/pii/S0149197023002287},
	doi = {10.1016/j.pnucene.2023.104793},
	abstract = {This article presents the development of a grid-to-rod fretting (GTRF) modeling methodology that utilizes dynamic mortar contact. We leverage a recently developed computational framework for modeling thermomechanical contact in dynamic simulations from the nuclear fuel performance code Bison. Usage of mortar contact ensures a smooth distribution of normal and frictional contact forces, displacements, and velocities on the contact interface, thus facilitating an accurate computation of wear. The integration within an advanced nuclear fuel performance code enables analysis of complex interactions between the fuel, cladding, and spacer grid. Such interactions include swelling, creep, fuel fragmentation, burnup, plenum pressure, and fission gas release. Our methodology is demonstrated via the modeling of two spacer grid geometries and the influence of fuel-cladding mechanical contact on the generation of fretting wear.},
	urldate = {2024-06-04},
	journal = {Progress in Nuclear Energy},
	author = {Recuero, Antonio and Lindsay, Alexander and Yushu, Dewen},
	month = sep,
	year = {2023},
	keywords = {Bison, Grid-to-rod fretting wear, Mortar finite element method, Nuclear fuel performance, Simulation},
	pages = {104793},
	file = {ScienceDirect Snapshot:/Users/huff/Zotero/storage/FHBVGWW6/S0149197023002287.html:text/html},
}

@techreport{project_introducing_2024,
	title = {Introducing yt 4.0: {Analysis} and {Visualization} of {Volumetric} {Data}},
	shorttitle = {Introducing yt 4.0},
	url = {https://yt-project.github.io/yt-4.0-paper/},
	language = {en-US},
	urldate = {2024-06-04},
	institution = {Manubot},
	author = {Project, The yt and Turk, Matthew and Goldbaum, Nathan J. and ZuHone, John A. and Hummels, Cameron and Ji, Suoqing and Lang, Meagan and Munk, Madicken and Smith, Britton and Kowalik, Kacper and Val-Borro, Miguel de and Coughlin, Jared W. and Cadiou, Corentin and Zingale, Michael and Orf, Leigh and Halbert, Kelton and Robert, Cl{\'e}ment and Havlin, Christopher and Tonnesen, Stephanie and Myers, Andrew and Gurvich, Alex and Narayanan, Desika and Skillman, Samuel W. and Huebl, Axel and Biondo, Elliott and Wetzel, Andrew and Strawn, Clayton and Lindsay, Alexander and Altay, Gabriel and Lau, Erwin T. and Smith, Aaron and Kim, Ji-hoon and Schive, Hsi-Yu and S, Navaneeth and O'Shea, Brian W. and Abel, Tom and Gondhalekar, Yash and Gray, William J. and Gnedin, Nickolay Y. and Joana, Cristian and Li, Yuan and Farber, Ryan Jeffrey and Miller, Jonah M. and Ryan, Michael and Silvia, Devin W. and Jackson, Robert and Arraki, Kenz and Dutta, Alankar and Ghosh, Ritali and Xie, Shaokun and Naiman, Jill P. and Hix, Ronan and Borrow, Josh and Dong, Bili and Streicher, Ole and Mumford, Stuart and Keller, Benjamin and Thompson, Benjamin and Grete, Philipp and Wise, John H. and Tsai, Shin-Rong and Wijers, Nastasha Anna and Yourself, Add},
	month = jun,
	year = {2024},
	note = {Publication Title: Manubot},
	file = {Full Text PDF:/Users/huff/Zotero/storage/KCKHB757/Project et al. - 2024 - Introducing yt 4.0 Analysis and Visualization of .pdf:application/pdf},
}

@inproceedings{giudicelli_latest_2023,
	address = {Washington D.C.},
	title = {Latest developments in the {MOOSE} fluid properties module},
	url = {https://www.osti.gov/biblio/2331257},
	abstract = {The fluid properties module in MOOSE serves a variety of fluid simulation applications based on MOOSE, including the MOOSE Navier Stokes module{\textasciitilde}{\textbackslash}cite\{moose\_ns\}, Pronghorn{\textasciitilde}{\textbackslash}cite\{pgh\}, SAM{\textasciitilde}{\textbackslash}cite\{sam\}, the MOOSE thermal hydraulics module, RELAP-7{\textasciitilde}{\textbackslash}cite\{relap7\} and subchannel{\textasciitilde}{\textbackslash}cite\{subchannel\}. It is used for coarse mesh multi-dimensional thermal-hydraulics{\textasciitilde}{\textbackslash}cite\{pgh\}, 1D systems analysis{\textasciitilde}{\textbackslash}cite\{sam,relap7\} in nuclear reactor analysis, and porous flow simulations{\textasciitilde}{\textbackslash}cite\{porous\} for underground gas storage and water seepage. The use of consistent fluid properties across fluid flow applications facilitates coupled simulations{\textasciitilde}{\textbackslash}cite\{anl\_sam\_pgh\}. The module offers a consistent set of interfaces to implement to create a new fluid property. There are numerous fluid properties of interest in the entirety of all fields of fluid flow simulations, and this is exacerbated by the use of different variable sets depending on the compressibility of the fluid. For single-phase fluids, the following variable sets may be used to compute fluid properties: (pressure, temperature) and (specific volume, specific internal energy). Some properties may also be computed using the (pressure, density) or the (specific volume, specific enthalpy) variable sets. In order to reduce the challenge of adding a new fluid property, properties may be implemented partially.},
	language = {English},
	urldate = {2024-06-04},
	booktitle = {{ANS} {Winter} 2023},
	publisher = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Giudicelli, Guillaume Louis and Lindsay, Alexander D. and Spaude, Benjamin and Isaacs, Steven},
	month = nov,
	year = {2023},
	note = {Report Number: INL/CON-23-73289-Rev000},
	file = {Full Text PDF:/Users/huff/Zotero/storage/XDNRPTYK/Giudicelli et al. - 2023 - Latest developments in the MOOSE fluid properties .pdf:application/pdf},
}

@misc{okyay_validation_2023-1,
	title = {Validation and {Comparison} of {HI}-{STORM} {Overpack} {Thermal}-{Hydraulic} {Model} with {MOOSE} and {NekRS}},
	url = {http://arxiv.org/abs/2308.15455},
	doi = {10.48550/arXiv.2308.15455},
	abstract = {Nuclear power is a significant source of electricity in the United States, but the average U.S. nuclear power plant is around 40 years old. Safe management of spent nuclear fuel (SNF) is a crucial aspect of the back end of the nuclear fuel cycle. SNF dry storage systems are increasingly popular as they represent an effective solution in this area, given the absence of a final disposal system. In particular, the spent fuel cask system (dry cask method) provides a feasible solution for maintaining SNF (\${\textbackslash}sim\$60 years) prior to the final disposal. The HI-STORM overpack and MPC-32 canister are the primary components of the HI-STORM 100 dry cask storage system. They remove heat from the system via natural circulation with no human intervention required. This characteristic provides passive heat removal while requiring little maintenance in dry cask storage systems. This project aims to validate and compare the capabilities of a thermal model of HI-STORM overpack developed using the Multiphysics Object-Oriented Simulation Environment (MOOSE) based on the author's previous study. MOOSE is an open-source framework developed by Idaho National Laboratory for multiscale, multiphysics simulations. This study will improve the capabilities of the thermal-hydraulic model of the HI-STORM dry cask storage system by producing high-fidelity results for the air circulation in the overpack. Large Eddy Simulations (LES) are performed using the open-source spectral element code NekRS, developed by Argonne National Laboratory (ANL), for simulating transitional and turbulent flows in complex geometries. NekRS will produce high-fidelity results for the HI-STORM overpack to assess the validity of the current thermal-hydraulic model.},
	urldate = {2024-06-04},
	publisher = {arXiv},
	author = {Okyay, Sinan and Merzari, Elia and Reger, David A. and Leite, Victor Coppo and Giudicelli, Guillaume and German, Peter and Lindsay, Alexander},
	month = aug,
	year = {2023},
	note = {arXiv:2308.15455 [physics]},
	keywords = {Physics - Fluid Dynamics},
	annote = {Comment: 12 pages, 9 figures, Proceedings of NURETH-20 Conference},
	file = {arXiv Fulltext PDF:/Users/huff/Zotero/storage/T8KQ73QU/Okyay et al. - 2023 - Validation and Comparison of HI-STORM Overpack The.pdf:application/pdf;arXiv.org Snapshot:/Users/huff/Zotero/storage/EIULQYJR/2308.html:text/html},
}

@techreport{andrs_nitrogen_2023,
	title = {Nitrogen {Fluid} {Properties}},
	url = {https://www.osti.gov/biblio/1997218},
	abstract = {This software is used to compute numerous properties for nitrogen.},
	language = {en},
	number = {nitrogen},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Andrs, David and Hansel, Joshua E. and Lindsay, Alexander D. and Slaughter, Andrew E. and Harbour, Logan and Permann, Cody and Giudicelli, Guillaume and Carlsen, Robert and Kunick, Matthias},
	month = jun,
	year = {2023},
	doi = {10.11578/dc.20230830.8},
}

@misc{andrs_idaholabhelium_2024,
	title = {idaholab/helium},
	copyright = {LGPL-2.1},
	url = {https://github.com/idaholab/helium},
	urldate = {2024-06-04},
	publisher = {Idaho National Laboratory},
	author = {Andrs, David and Lindsay, Alexander D. and Hansel, Joshua E. and Slaughter, Andrew E. and Permann, Cody and Harbour, Logan and Carlsen, Robert and Kunick, Matthias},
	month = jun,
	year = {2024},
	note = {original-date: 2023-06-14T22:37:20Z},
}

@techreport{andrs_helium_2023,
	title = {Helium {Fluid} {Properties}},
	url = {https://www.osti.gov/biblio/1997214},
	abstract = {This software is used to compute numerous properties for helium.},
	language = {en},
	number = {helium},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Andrs, David and Lindsay, Alexander D. and Hansel, Joshua E. and Slaughter, Andrew E. and Permann, Cody and Harbour, Logan and Carlsen, Robert and Kunick, Matthias},
	month = jun,
	year = {2023},
	doi = {10.11578/dc.20230830.5},
}

@techreport{andrs_carbon_2023,
	title = {Carbon {Dioxide} {Fluid} {Properties}},
	url = {https://www.osti.gov/biblio/1997216},
	abstract = {This software is used to compute numerous properties for the liquid and vapor phases of carbon dioxide.},
	language = {en},
	number = {carbon\_dioxide},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Andrs, David and Permann, Cody and Hansel, Joshua E. and Harbour, Logan and Lindsay, Alexander D. and Giudicelli, Guillaume and Kunick, Matthias},
	month = jun,
	year = {2023},
	doi = {10.11578/dc.20230830.6},
}

@misc{noauthor_idaholabcarbon_dioxide_2024,
	title = {idaholab/carbon\_dioxide},
	copyright = {LGPL-2.1},
	url = {https://github.com/idaholab/carbon_dioxide},
	urldate = {2024-06-04},
	publisher = {Idaho National Laboratory},
	month = jun,
	year = {2024},
	note = {original-date: 2023-06-14T22:41:56Z},
}

@inproceedings{martin_recuero_practical_2023,
	address = {St. Louis, Missouri},
	title = {On {Practical} {Aspects} of {Variational} {Consistency} in {Contact} {Dynamics}},
	url = {https://www.osti.gov/biblio/1988114},
	abstract = {Usage of contact mechanics methodologies is a pervasive modeling requirement in dynamic simulations. While for some trivial problems, solutions taken from analytical geometry are available, use of a finite element framework is common to achieve formulation generality. This work explores two dynamic contact formulations: one based on the traditional node-to-segment (NTS) approach, and a variationally consistent segment-to-segment (STS) mortar formulation. The NTS formulation employed here enforces the constraints kinematically (i.e., the interpenetration is enforced to the solver tolerance), whereas the mortar approach uses Lagrange multipliers to enforce the contact constraints. Both approaches are implemented in the open-source finite element framework Multiphysics Object-Oriented Simulation Environment (MOOSE). The results highlight two relevant contact-interface-related dynamic phenomena in finite element simulations. First, stabilization of contact constraints is discussed, taking into account the evolution of the total energy in a benchmark problem. Second, the influence of finite element discretization on both of the aforementioned contact formulations is analyzed by exercising a large-deformation example with continuous relative sliding. Variationally consistent contact approaches such as the mortar formulation lead to improved energy preservation and avoid spurious excitation of the system's frequencies. This is especially relevant in settings where inertia and vibrations are of importance.},
	language = {English},
	urldate = {2024-06-04},
	booktitle = {{ASME} {IDETC}-{CIE} 2022 - {International} {Design} {Engineering} {Technical} {Conferences} \& {Computers} and {Information} in {Engineering} {Conference}},
	publisher = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Martin Recuero, Antonio and Lindsay, Alexander D.},
	month = may,
	year = {2023},
	note = {Report Number: INL/CON-22-65883-Rev000},
	file = {Full Text PDF:/Users/huff/Zotero/storage/CZAZJ5CJ/Martin Recuero and Lindsay - 2023 - On Practical Aspects of Variational Consistency in.pdf:application/pdf},
}

@inproceedings{okyay_development_2023,
	title = {Development of a {Hi}-{Storm} {Overpack} and {Mpc}-32 {Thermal}-{Hydraulic} {Model} with the {Moose} {Framework}},
	volume = {2023.30},
	url = {https://www.jstage.jst.go.jp/article/jsmeicone/2023.30/0/2023.30_1036/_article/-char/ja/},
	doi = {10.1299/jsmeicone.2023.30.1036},
	abstract = {Nuclear power is a significant source of electricity in the United States, but the average U.S. nuclear power plant is around 40 years old. Safe management of spent nuclear fuel (SNF) is a key aspect of the back end of the nuclear fuel cycle, and SNF dry storage systems are increasing in popularity as they represent an effective solution in this area given the absence of a final disposal system. In particular, the spent fuel cask system (dry cask method) provides a feasible solution for maintaining SNF (?60 years) prior to the final disposal.The HI-STORM overpack and MPC-32 canister are the primary components of the HI-STORM 100 dry cask storage system. They remove heat from the system via natural circulation with no human intervention required. This characteristic provides passive heat removal while requiring little maintinence in dry cask storage systems.This project aims to validate and improve the capabilities of a thermal model of the MPC-32 canister and HI-STORM overpack, using the Multiphysics Object-Oriented Simulation Environment (MOOSE) based on the previous study of the author. MOOSE is an open-source framework developed by Idaho National Laboratory for multiscale, multiphysics simulations. This study will improve the capabilities of the thermal-hydraulic model of the HI-STORM dry cask storage system. The dry cask storage system often uses the chimney model to model the natural circulation of the air in the overpack storage systems. This study offers a new reliable and inclusive strategy for resolving issues pertaining to dry cask storage. The solution strategy eliminates the assumptions of Bernoulli equation in the chimney model.In this study, we investigate and demonstrate MOOSE{\textquoteright}s thermal-hydraulics modeling capabilities on a dry cask problem, including the modeling of natural circulation, heat transfer, and porous flow. Additionally, we will demonstrate a validation case with the thermal model to evaluate the overall performance of the model.},
	booktitle = {Proceedings of the ... {International} {Conference} on {Nuclear} {Engineering}. {Book} of abstracts : {ICONE}},
	author = {Okyay, Sinan and Merzari, Elia and Reger, David Alan and Giudicelli, Guillaume and Leite, Victor Coppo and Lindsay, Alexander},
	year = {2023},
	keywords = {HI-STORM 100, MOOSE, Multi-Purpose Canister, Natural Circulation Loops, Spent Nuclear Fuel},
	pages = {1036},
	file = {J-Stage - Snapshot:/Users/huff/Zotero/storage/W5WD4GPW/ja.html:text/html},
}

@inproceedings{giudicelli_assembling_2022,
	address = {Phoenix, AZ},
	title = {Assembling {Multiphysics} {Nuclear} {Reactor} {Simulations} {Using} the {MOOSE} {Framework}},
	url = {https://www.osti.gov/biblio/2337502},
	abstract = {The Multiphysics Object Oriented Simulation Environment (MOOSE) [1] is an open-source, parallel finite element framework which provides the foundation for many advanced modeling and simulation tools developed under the Department of Energy (DOE) Nuclear Energy Advanced Modeling and Simulation (NEAMS) Program [2] for the analysis of advanced reactors. The MOOSE framework provides the common foundational capability on which many NEAMS codes for reactor analysis are built. The MOOSE framework also includes several systems to assemble unique workflows and couplingamong MOOSE-based applications. In particular, the MultiApp and Transfer Systems are widely used to assemble different MOOSE-based or MOOSE-wrapped physics applications together to perform loosely or tightly coupled multiphysics simulations. The National Reactor Innovation Center (NRIC) Virtual Test Bed (VTB) [3] hosts publicly available nuclear reactor multiphysics simulation examples which leverage MOOSE{\textquoteright}s MultiApp System to meet the modeling needs of different reactor types. The flexibility and robustness of coupling provided by MOOSE permits rapid development of coupled physics models for a wide range of reactor types and events},
	language = {English},
	urldate = {2024-06-04},
	booktitle = {American {Nuclear} {Society} {Winter} {Meeting} 2022},
	publisher = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Giudicelli, Guillaume Louis and Permann, Cody J. and Kong, Fande and Gaston, Derek R. and Abdelhameed, A. and Shemon, Emily and Miao, Yinbin and Lindsay, A.},
	month = nov,
	year = {2022},
	file = {Full Text PDF:/Users/huff/Zotero/storage/V66V8VLV/Giudicelli et al. - 2022 - Assembling Multiphysics Nuclear Reactor Simulation.pdf:application/pdf},
}

@inproceedings{okyay_hi-storm_2022,
	address = {Phoenix, AZ},
	title = {{HI}-{STORM} {Overpack} and {MPC}-32 {Thermal}-{Hydraulic} {Model} with {MOOSE} {Framework}},
	url = {https://www.osti.gov/biblio/2331393},
	abstract = {Nuclear power is a significant source of electricity in the United States, but the average age of nuclear power plants is around 40 years old. The safe management of the spent nuclear fuel (SNF) is a key aspect of the back-end of the nuclear fuel cycle. Spent fuel dry storage systems are becoming a popular and effective solution in this area, given the absence of a final disposal system. The spent fuel cask system (dry cask method) provides a feasible solution to maintain spent fuel for 60 years before final disposal. Dry cask storage has many characteristics that make it attractive. It fulfills the safety requirements of the Nuclear Regulatory Commission (NRC) while providing modularity and flexibility to contractors. The HI-STORM overpack and MPC-32 canister are the main parts of the HI-STORM 100 dry cask storage system. These components remove heat from the system using natural circulation, requiring no human intervention. This is the characteristic that provides passive heat removal and low maintenance features in dry cask storage systems. To develop a thermal model for a dry cask storage system, the physics behind the system should be defined clearly. There are two natural circulation loops in the system; circulation of helium cools down the nuclear assemblies in the MPC, while circulation of air cools down the walls of the MPC. This work aims to develop a thermal model of the MPC-32 canister and HI-STORM overpack using the Multiphysics Object-Oriented Simulation Environment (MOOSE). MOOSE is an open-source framework developed by Idaho National Laboratory (INL) for multiscale, multiphysics simulations. In this study, we will investigate and demonstrate the thermal-hydraulics modeling capabilities of the MOOSE framework, including natural circulation, heat transfer, and porous flow.},
	language = {English},
	urldate = {2024-06-04},
	booktitle = {{ANS} {Winter} {Meeting} 2022},
	publisher = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Okyay, Sinan and Kong, Fande and German, Peter and Giudicelli, Guillaume Louis and Lindsay, Alexander D. and Reger, David Alan and Merzari, Elia and Leite, Victor Coppo},
	month = nov,
	year = {2022},
	doi = {10.1299/jsmeicone.2023.30.1036},
	note = {ISSN: 2424--2934
Issue: 0
Volume: 2023.30},
	file = {Full Text PDF:/Users/huff/Zotero/storage/23HANGGW/Okyay et al. - 2022 - HI-STORM Overpack and MPC-32 Thermal-Hydraulic Mod.pdf:application/pdf},
}

@techreport{lindsay_neams_2022,
	title = {{NEAMS} {Technical} {Area} {Support} in {MOOSE}},
	url = {https://www.osti.gov/biblio/1986001},
	abstract = {The Multiphysics Object-Oriented Simulation Environment (MOOSE) framework is a foundational capability used by the Nuclear Energy Advanced Modeling and Simulation (NEAMS) program to create over 15 different simulation tools for advanced nuclear reactors. Due to this ubiquity, improvements to the framework in support of modeling and simulation goals are critical to the program. These improvements can take many forms, including optimization, improved user experience, streamlined application programming interfaces (APIs), parallelism, and new capabilities. The work transcribed in this report was conducted in direct support of the simulation tools and has already been deployed. The capabilities outlined in this report include a factor of 10{\textasciicircum}4 improvement in dependency resolution speed, sorting of user objects, ability to compute residuals and Jacobians together, transfer fixes, support for the mortar method in finite volume discretizations, addition of generalized advection schemes for fluid simulations, 10{\textasciicircum}2 speedup in some Griffin simulations due to a new matrix-only solve type, and much more.},
	language = {English},
	number = {INL/RPT-22-69424-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Lindsay, Alexander D. and Giudicelli, Guillaume Louis and Permann, Cody J.},
	month = sep,
	year = {2022},
	doi = {10.2172/1986001},
	file = {Full Text PDF:/Users/huff/Zotero/storage/XJ4829VN/Lindsay et al. - 2022 - NEAMS Technical Area Support in MOOSE.pdf:application/pdf},
}

@inproceedings{icenhour_electromagnetics_2022,
	address = {Cambridge, MA, USA},
	title = {Electromagnetics and {Advanced} {Manufacturing} {Simulation} {Development} within the {MOOSE} {Ecosystem}},
	url = {https://www.osti.gov/biblio/1882589},
	abstract = {The MOOSE electromagnetics module (EMM) was developed to provide a general simulation tool for modeling a wide range of problems encountered in computational electromagnetics and enable MOOSE and MOOSE-based application coupling to Maxwell's equations to solve a wide class of new problems. Development of the electromagnetics module has also enabled development of new advanced manufacturing models in the MOOSE ecosystem, including that of the electric field-assisted sintering (EFAS) process. Recent results from this effort show good agreement with experimental results, and these two capabilities will be used in future projects to develop models for novel materials development and manufacturing for extreme environments.},
	language = {English},
	urldate = {2024-06-04},
	booktitle = {3rd {Computational} {Physics} {School} for {Fusion} {Research}},
	publisher = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Icenhour, Casey T. and Pitts, Stephanie A. and Lindsay, Alexander D.},
	month = aug,
	year = {2022},
	note = {Report Number: INL/CON-22-68724-Rev000},
	file = {Full Text PDF:/Users/huff/Zotero/storage/QZT2EAXI/Icenhour et al. - 2022 - Electromagnetics and Advanced Manufacturing Simula.pdf:application/pdf},
}

@misc{aagesen_marmot_2022,
	title = {Marmot {V2}},
	shorttitle = {Marmot {V2}; {006081MLTPL00}},
	url = {https://www.osti.gov/biblio/1862850},
	abstract = {MARMOT is a robust numerical tool for mesoscale modeling of fuel performance developed under the NEAMS Fuels technical area to predict the coevolution of microstructure and properties in fuel and cladding materials. MARMOT accomplishes this using the phase field method coupled with finite strain mechanics and heat conduction. MARMOT is based on the open source Multiphysics Object-Oriented Simulation Environment (MOOSE) and solves the coupled partial differential equations defining the physics using the finite element method. MARMOT is being developed in order to facilitate the development of improved materials models for fuel performance, but it is also being developed as a powerful tool in and of itself for the simulation of mesoscale fuel performance.},
	urldate = {2024-06-04},
	publisher = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Aagesen, Larry K. and Schwen, Daniel and Permann, Cody and Hales, Jason and Jiang, Wen and Jokisaari, Andrea M. and Biswas, Sudipta and Miller, Jason and Lindsay, Alexander D. and Harbour, Logan H. and Icenhour, Casey T. and Yushu, Dewen and Gamble, Kyle and Gaston, Derek and Hansel, Joshua B. and Kong, Fande and Harter, Jackson R. and Spencer, Benjamin and Schunert, Sebastian and Pitts, Stephanie A. and Yu, Jianguo and Tonks, Michael and Bai, Xianming and Ahmed, Karim and Zhang, Yongfeng and Millett, Paul and Andersson, Anders and Matthews, Christopher},
	month = apr,
	year = {2022},
	file = {Snapshot:/Users/huff/Zotero/storage/2SG6LTW6/1862850.html:text/html},
}

@article{inl_software_stm_2022,
	title = {{STM}: {MOOSE}-{Based} {Scalar} {Field} {Transport} {Modeling}},
	shorttitle = {{STM}},
	abstract = {This new MOOSE module focuses on the transport of scalar fields. It will provide a way to describe the conservation laws of scalars, including the effects of advection (bulk fluid motion), diffusion, and reactivity. It will rely on at least two existing MOOSE modules, the chemical reactions module and thermal hydraulics module (THM), to compute reactivity and advective terms, respectively. The new scalar transport module (STM) will likely also draw on the component syntax of THM to make input files more readable for users. It may also use the electromagnetics module to compute ionic species transport in electromagnetic fields. It will be helpful for any groups that need to calculate scalar transport, such as precursor transport in molten salt reactors and ion and neutral transport in (fusion) plasmas.},
	journal = {Nuclear Science \& Technology, Advanced Scientific Computing},
	author = {INL Software and Lindsay, Alexander and Giudicelli, Guillaume},
	year = {2022},
}

@inproceedings{permann_assembling_2022,
	title = {Assembling {Multiphysics} {Nuclear} {Reactor} {Simulations} {Using} the {MOOSE} {Framework}},
	volume = {127},
	doi = {10.13182/T127-39768},
	abstract = {MOOSE-based (or MOOSE-wrapped) physics applications such as Griffin, Pronghorn, and Bison may be assembled into a customized multiphysics workflow for reactor analysis using the MultiApp and Transfer systems within MOOSE. The plug-and-play capabilities of MOOSE's MultiApp system allow a common suite of reactor analysis codes to be leveraged for multiple reactor types while tailoring multiphysics coupling and workflows to each reactor type and event using input file syntax only. This plug- and-play paradigm allows rapid development of multiphysics modeling capabilities for a diverse set of problems by non-expert users. New features include the ability for MOOSE to transfer data between {\textquotedblleft}sibling{\textquotedblright} applications, rather than just between parent and child, and new syntax to facilitate data transfer between codes using different coordinate systems. The VTB hosts numerous nuclear reactor multiphysics examples using the MOOSE capabilities described here. Documentation on multiphysics coupling for nuclear reactors using MOOSE is also available on the VTB. Continuous integration testing is performed on VTB code inputs to ensure they are kept up to date and functional with most recent code versions. {\textcopyright} 2022 American Nuclear Society. All rights reserved.},
	language = {English},
	author = {Permann, C. and Lindsay, A. and Giudicelli, G. and Kong, F. and Gaston, D. and Shemon, E. and Miao, Y. and Abdelhameed, A.},
	year = {2022},
	note = {ISSN: 0003-018X
Issue: 1},
	pages = {948--951},
	file = {Snapshot:/Users/huff/Zotero/storage/ZSJ7L4SK/display.html:text/html},
}

@inproceedings{dechant_coupling_2022,
	title = {Coupling {Finite} {Element} and {Finite} {Volume} within the {Plasma} {Fluid} {Code}: {Zapdos}},
	shorttitle = {Coupling {Finite} {Element} and {Finite} {Volume} within the {Plasma} {Fluid} {Code}},
	url = {https://ui.adsabs.harvard.edu/abs/2022APS..GECDR1002D},
	abstract = {This work focuses on adding capability to couple finite element (FE) variables into finite volume (FV) physics for the open-source multi-fluid plasma code, Zapdos, within INL's Multiphysics Object-Oriented Simulation Environment (MOOSE). This coupling can allow for improvement of multiphysics simulations where one set of physics is best suited for an FE discretization, while another set is best suited for an FV discretization. Plasma dynamics is a fitting example where the electromagnetic field equations are solved with FE and the fluid flow is solved with FV. The new FE to FV coupling method can be summarized as taking the element or face average of the FE variable value or gradient and applying that quantity directly in the FV equation objects. Verification and validation (V\&V) were conducted based on Zapdos FE-only V\&V efforts. Verification included method of manufactured solutions (MMS) with spatial and temporal convergence studies. These MMS studies were modularized, such that simple decoupled physics to fully coupled multi-fluid problems were studied. Validation included benchmarking with FE-only simulations to investigate the benefits of FE-FV coupling over the traditional FE-only simulations. Initial V\&V studies show good alignment to theory and previous simulation. NSF program for Software Infrastructure for Sustained Innovation (NSF-SI2) under award 1740300, the DOE-NEUP fellowship program, as well as a generous donation from Applied Materials Inc.},
	urldate = {2024-06-04},
	booktitle = {{APS} {Gaseous} {Electronics} {Conference} 2022},
	author = {Dechant, Corey and Icenhour, Casey and Gall, Grayson and Keniley, Shane and Lindsay, Alexander and Curreli, Davide and Shannon, Steven},
	month = jan,
	year = {2022},
	note = {Conference Name: APS Annual Gaseous Electronics Meeting Abstracts
ADS Bibcode: 2022APS..GECDR1002D},
	pages = {DR1.002},
}

@misc{noauthor_idaholabmalamute_2024,
	title = {idaholab/malamute},
	copyright = {LGPL-2.1},
	url = {https://github.com/idaholab/malamute},
	abstract = {Advanced manufacturing modeling and simulation},
	urldate = {2024-06-04},
	publisher = {Idaho National Laboratory},
	month = may,
	year = {2024},
	note = {original-date: 2023-03-08T16:54:13Z},
	keywords = {advanced-manufacturing, finite-element-method, finite-volume-method, moose-framework, multiphysics, object-oriented, simulation},
}

@techreport{lindsay_moose_2021,
	title = {Moose {Application} {Library} {For} {Advanced} {Manufacturing} {Utilities}},
	url = {https://www.osti.gov/biblio/1880788},
	abstract = {MALAMUTE combines MOOSE module functionality with realistic materials and geometries for arbitrary-Eulerian-Lagrangian (ALE) and level-set based laser melting and welding applications and electric-field assisted sintering (EFAS) applications.},
	language = {en},
	number = {MALAMUTE; 006101WKSTN00},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Lindsay, Alexander D. and Jiang, Wen and Pitts, Stephanie A. and Aagesen, Larry K. and Icenhour, Casey T.},
	month = jul,
	year = {2021},
	file = {Snapshot:/Users/huff/Zotero/storage/WWSCCSMA/1880788.html:text/html},
}

@article{inl_software_malamute_2021,
	title = {{MALAMUTE}: {Simulation} {Code} for {Advanced} {Manufacturing} {Processes}},
	shorttitle = {{MALAMUTE}},
	abstract = {The MOOSE Application Library for Advanced Manufacturing UTilitiEs, or MALAMUTE, is a simulation code that combines MOOSE module functionality with realistic materials and geometries for various advanced manufacturing processes such as laser melting, welding, and electric-field assisted sintering. Leveraging the existing MOOSE module, MOOSE framework, libMesh, and PETSc capabilities, MALAMUTE provides users with a head start on tackling advanced manufacturing modeling and simulation. MOOSE and its upstream libraries already contain sophisticated capabilities, such as mechanical contact, heat transport, phase field, level set, electromagnetics, ALE, solid mechanics, and fluid mechanics. MALAMUTE adds realistic material models and geometries to this robust platform, making it a unique starting point for physics capabilities based on finite element, finite volume, and nonlinear solver technology.This software is open source and available at no cost.},
	journal = {Nuclear Science \& Technology, Advanced Scientific Computing, Nuclear Fuels \& Materials},
	author = {INL Software and Lindsay, Alexander and Jiang, Wen and Pitts, Stephanie and Aagesen, Larry and Icenhour, Casey},
	year = {2021},
}

@inproceedings{dechant_validation_2021,
	address = {Virtual},
	title = {Validation and {Verification} {Methods} for the {Open} {Source} {Code}: {Zapdos}},
	shorttitle = {Validation and {Verification} {Methods} for the {Open} {Source} {Code}},
	url = {https://ui.adsabs.harvard.edu/abs/2021APS..GECC14002D},
	abstract = {Zapdos is an open source, multi-fluid plasma code based in MOOSE (Multiphysics Object Oriented Simulation Environment). Validation and verification studies were done within three broad studies. First, temporal and spatial convergence studies were conducted by using the method of manufactured solutions (MMS), where different coupling configurations were tested. Second, Zapdos results were compared to previous simulations for a push-pull RF discharge of argon in the GEC reference cell for 1 Torr in 1D, and 1 Torr and 100 mTorr in 2D. Finally, a parametric study was done for argon at varying pressure and voltage for RF discharges at 13.56 MHz in a GEC reference cell and compared to previous experimental results for electron and metastable densities that used microwave interferometry and laser-induced fluorescence, respectively. The MMS study results resembled the expected theoretically convergence trends with electron mean energy being particular sensitive. The comparisons to previous simulations matched within reason. Current experiment validation results follow previous experimental trend, with some deviation for pressure near 100 mTorr. A possible reason for those deviations could be due to the current assumptions within Zapdos based on the fluid approximation of plasmas.},
	urldate = {2024-06-04},
	booktitle = {{APS} {Gaseous} {Electronics} {Conference} 2021},
	author = {Dechant, Corey and Icenhour, Casey and Gall, Grayson and Keniley, Shane and Lindsay, Alexander and Curreli, Davide and Shannon, Steven},
	month = jan,
	year = {2021},
	note = {Conference Name: APS Annual Gaseous Electronics Meeting Abstracts
ADS Bibcode: 2021APS..GECC14002D},
	pages = {CT14.002},
}

@article{inl_software_tmap8_2020,
	title = {{TMAP8}: {Simplifying} {Scalar} {Transport} {Modeling} for {Fusion}, {Plasma}, and {Chemical} {Analysis}},
	shorttitle = {{TMAP8}},
	url = {https://www.osti.gov/biblio/1764414},
	doi = {10.11578/dc.20210205.2},
	abstract = {TMAP8, a MOOSE application, simplifies 0-1D scalar diffusion-reactive transport with its unique custom syntax. Catering to users in low-temperature plasma, fusion, and chemistry, the application provides an accessible entry point for those new to MOOSE. Its competitive advantage stems from its integration with MOOSE's mature multiphysics capabilities, allowing complex multiscale modeling in conjunction with other MOOSE applications. TMAP8's simple syntax, built on the robust foundation of libMesh and PETSc, enables rapid setup of diffusive-reactive and heat conduction models.This software is open source and available at no cost.},
	language = {en},
	journal = {Nuclear Science \& Technology, Advanced Scientific Computing, Nuclear Fuels \& Materials},
	author = {INL Software and Lindsay, Alexander and Simon, PC},
	year = {2020},
}

@inproceedings{icenhour_continued_2020,
	address = {San Diego, CA, USA},
	title = {Continued {Validation} {Studies} using the {MOOSE} {Framework} for {Plasma} {Simulation} with {Electromagnetics}},
	url = {https://www.osti.gov/biblio/1974891},
	abstract = {Resources and tools for the modeling and simulation of low-temperature plasma (LTP) discharges are increasingly vital to progress in the field in order to properly characterize and study complex source designs and plasma chemistries beyond the scope of traditional diagnostics. Open-source software provides powerful platforms for this work and can enable community-driven LTP R\&D. Within the Multiphysics Object-Oriented Simulation Environment (MOOSE) open-source framework [1], capabilities have been demonstrated in the areas of plasma fluids (Zapdos [2]), plasma chemistry (CRANE [3]), and general electromagnetic wave theory (Electromagnetic Library for Kinetics \& fluids [ELK] [4]). ELK has since been coupled to Zapdos/CRANE to enable fully coupled electromagnetic plasma simulations. This talk will detail the continued validation efforts and discuss Zapdos-ELK-CRANE code coupling with various-low temperature plasma sources. The impact of fully coupled electromagnetics on process parameters (e.g., temperature and electron/ion energy) versus an electrostatic description will also be discussed. [1] Permann et al., SoftwareX, 11 (2020) 100430. [2] Lindsay et al., J. Phys. D: Appl. Phys. 49 (2016) 235204. [3] Keniley et al., Talk, GEC Session DT3.00002 (2019). [4] Icenhour et al., Talk, GEC Session RR1.00006 (2019). Acknowledgements: INL Graduate Fellowship Program, NSF SI2 Grant 1740300, U.S. Dept. of Energy Office of Science Graduate Student Research Program},
	language = {English},
	urldate = {2024-06-04},
	booktitle = {Gaseous {Electronics} {Conference} 2020},
	publisher = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Icenhour, Casey T. and DeChant, Corey and Lindsay, Alexander D. and Green, David and Shannon, Steven},
	month = oct,
	year = {2020},
	file = {Full Text PDF:/Users/huff/Zotero/storage/Y39JBXFP/Icenhour et al. - 2020 - Continued Validation Studies using the MOOSE Frame.pdf:application/pdf},
}

@article{inl_software_finite-volume_2020,
	title = {Finite-volume {Compressible} {Navier} {Stokes} ({CNSFV}) in {MOOSE}},
	url = {https://inlsoftware.inl.gov/product/cnsfv},
	abstract = {MOOSE CNSFV is a finite-volume implementation for solving compressible Navier-Stokes equations. It provides a stable framework for computational fluid dynamics, using finite-volumes instead of finite-elements. The unique feature of MOOSE is its ability to couple with other physics, including finite element methods. This allows for robust convergence of multiphysics problems. Inputs for MOOSE CNSFV include user-specified meshes and boundary conditions, with outputs of compressible flow variables. By solving fluid dynamics and solid mechanics simultaneously, MOOSE offers a unique and powerful capability. This sets it apart from alternatives that rely on Picard coupling, which may have issues with convergence. Using MOOSE can save costs on expensive commercial licenses and enhance the reputation of INL and other DOE partners.},
	journal = {Nuclear Science \& Technology, Advanced Scientific Computing},
	author = {INL Software and Lindsay, Alexander and Carlsen, Robert and Schunert, Sebastian and MacDonald, Nolan},
	year = {2020},
}

@article{inl_software_moose_2020,
	title = {{MOOSE} {Framework} {Electromagnetics} ({EM}) {Module}},
	abstract = {The MOOSE Framework Electromagnetics (EM) Module provides general EM simulation capabilities for the MOOSE ecosystem. The EM Module solves Maxwell's equations in a Helmholtz wave equation form for electric and magnetic fields in multi-dimensional scenarios, with boundary and interface conditions for wave launching, reflection/transmission, wave absorption, and generic electrostatic contact as well as current density point and volumetric sources.},
	language = {American English},
	journal = {Nuclear Science \& Technology, Advanced Scientific Computing},
	author = {INL Software and Icenhour, Casey and Lindsay, Alexander},
	year = {2020},
}

@article{inl_software_fsi_2020,
	title = {{FSI}: {Fluid} {Strucure} {Interaction} {Module}},
	shorttitle = {{FSI}},
	abstract = {The fluid structure interaction (FSI) module is for modeling physics at the interface between fluid and deformable solid subdomains. FSI is relevant to many applications, including grid-to-rod fretting, blood flow, aircraft wing design, and sound generation. We anticipate customers throughout DOE, academia, and industry.},
	journal = {Nuclear Science \& Technology, Advanced Scientific Computing},
	author = {INL Software and Lindsay, Alexander and Kong, Fande and Dhulipala, Lakshmi},
	year = {2020},
}

@inproceedings{shannon_open_2020,
	title = {Open source plasma simulation in the {MOOSE} framework},
	volume = {2020},
	url = {https://ui.adsabs.harvard.edu/abs/2020APS..DPPN10010S},
	abstract = {The Multi-Physics Object Oriented Simulation Environment (MOOSE) is an open source framework originally developed for nuclear reactor simulation. Because of its original intention, the framework has a very well established development environment for deploying, tracking, and updating applications and insuring that code is well documented and verified. Recently, MOOSE has grown into a broader range of applications as the need for open source environments in science has grown. In this talk, we will present a brief overview of the MOOSE ecosystem and present results from three recently developed plasma applications: 1.) ZAPDOS, a two-fluid plasma simulation tool, 2.) CRANE, a plasma chemistry application for integration of complex chemical pathways into plasma simulation through ZAPDOS, and 3.) ELK, an electromagnetic solver designed to couple to ZAPDOS and enable solution of a broader class of plasma problems. These results will combine new discoveries and validation efforts, with emphasis on how the MOOSE ecosystem works to advance open source community development of plasma simulation tools.},
	urldate = {2024-06-04},
	booktitle = {{APS} {Division} of {Plasma} {Physics} {Meeting} 2020},
	author = {Shannon, Steven and Curreli, Davide and Dechant, Corey and Gall, Grayson and Green, David and Icenhour, Casey and Keniley, Shane and Lindsay, Alexander},
	month = jan,
	year = {2020},
	note = {Conference Name: APS Division of Plasma Physics Meeting Abstracts
ADS Bibcode: 2020APS..DPPN10010S},
	pages = {NM10.010},
}

@inproceedings{dechant_validations_2020,
	title = {Validations for {Improvements} of the {Open} {Source} {Plasma} {Code}, {Zapdos}},
	url = {https://ui.adsabs.harvard.edu/abs/2020APS..GECQW2003D},
	abstract = {The Zapdos application is an open source finite element code for modeling plasma using the multi-fluid method based in the MOOSE framework. Comparison work of CCP discharges was performed between Zapdos, previous 1D and 2D modeling efforts, and experimental efforts undertaken at NCSU and elsewhere. The aim of these comparisons was to investigate the current limitations within the fluid code and improve upon them by including additional plasma behaviors as well as improve overall simulation performance. Surface boundaries, species temperatures, and field solutions were investigated during the validation efforts. Studied phenomena included DC self-biasing on the surfaces of RF powered electrodes and gas heating effects on the background gas and ions. To reduce the simulation wall time for the large number of RF cycles needed to reach a periodic steady state, an accelerator based on a modified shooting method was added to Zapdos. For the experimental comparisons, results from the GEC reference cell and the Medusa CCP at NCSU were used for pressures in the Torr range, while results from the COST reference jet were used for atmospheric plasmas. This work is supported through NSF Grant SI2-1740300 and the DOE-NEUP graduate fellowship program.},
	urldate = {2024-06-04},
	booktitle = {{APS} {Gaseous} {Electronics} {Conference} 2020},
	author = {Dechant, Corey and Xiao, Yuhua and Icenhour, Casey and Keniley, Shane and Lindsay, Alexander and Curreli, Davide and Shannon, Steven},
	month = jan,
	year = {2020},
	note = {Conference Name: APS Annual Gaseous Electronics Meeting Abstracts
ADS Bibcode: 2020APS..GECQW2003D},
	pages = {QW2.003},
}

@inproceedings{icenhour_validation_2019,
	address = {College Station, Texas, USA},
	title = {Validation {Studies} using {ELK} and the {Open}-{Source} {MOOSE} {Framework} {Application} {Zapdos} for {Electromagnetic} {Coupled} {Plasma} {Simulation}},
	url = {https://www.osti.gov/biblio/1574011},
	abstract = {An open source simulation platform that captures electromagnetics, plasma chemistry, and fluid treatment of the plasma domain would be a powerful tool for studying low temperature plasma (LTP) phenomena. Within the Multiphysics Object-Oriented Simulation Environment (MOOSE) open source framework, ELK, CRANE, and Zapdos are combined to provide open source simulation capability for the LTP community. This talk presents continued validation of the general electromagnetic (EM) simulation tool ELK (Electromagnetic Library for Kinetics \& fluids). Previous validation efforts focused on simulating standard waveguide and antenna benchmarks in vacuum and linear dielectrics, but ELK has since been coupled with the MOOSE-based plasma fluid application Zapdos [Lindsay et al 2016 J. Phys. D: Appl. Phys. 49 235204] to perform radio-frequency (rf) capacitively coupled plasma (CCP) system simulation. Plasma validation efforts initially focused on electrostatic benchmarks to demonstrate ELK-Zapdos code coupling and then moved to electromagnetic benchmarks based on interesting geometries and conditions (VHF effects in a CCP reactor, microwave heating, etc.). Results and progress in these efforts will be summarized and discussed.},
	language = {English},
	urldate = {2024-06-04},
	booktitle = {Gaseous {Electronics} {Conference} 2019,},
	publisher = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Icenhour, Casey T. and DeChant, Corey and Lindsay, Alexander D. and Martineau, Richard C. and Green, David and Shannon, Steven},
	month = oct,
	year = {2019},
	note = {Report Number: INL/CON-19-54135-Rev000},
	file = {Full Text PDF:/Users/huff/Zotero/storage/CTPFEDQW/Icenhour et al. - 2019 - Validation Studies using ELK and the Open-Source M.pdf:application/pdf},
}

@inproceedings{icenhour_elk_2018,
	address = {Oregon Convention Center, Portland, OR},
	title = {Elk: {A} {New} {MOOSE} {Framework} {Application} for {Radio}-frequency {Electromagnetics}},
	shorttitle = {Elk},
	url = {https://www.osti.gov/biblio/1498780},
	abstract = {A new tool in-development for general electromagnetic (EM) simulation for modeling radio-frequency (rf) systems is presented. The primary motivation for development of this tool is to leverage the flexibility and high-performance-computing capability of the Multiphysics Object-Oriented Simulation Environment (MOOSE) Framework developed by Idaho National Laboratory (INL) for complex EM problems. A MOOSE application (or MOOSE App) enables the end user to create a fully-functional simulation scenario without needing explicit knowledge of the underlying finite-element weak form implementation. MOOSE combines the libMesh library and the PetSc suite as the finite element and solver libraries, giving a robust platform for solving highly non-linear, coupled sets of PDEs such as those found in EM and plasma physics problems. Initial validation efforts have included standard waveguide and antenna benchmarks with the current focus being field validation against the well-known capacitively-coupled GEC Reference Cell (GEC-CCP). The results of this effort will be outlined and discussed. Future work plans including cold-plasma rf wave propagation studies and coupling to the plasma fluid MOOSE App, Zapdos [Lindsay et al 2016 J. Phys. D: Appl. Phys. 49 235204], will also be discussed.},
	language = {English},
	urldate = {2024-06-04},
	booktitle = {Gaseous {Electronics} {Conference} 2018},
	publisher = {Idaho National Lab. (INL), Idaho Falls, ID (United States)},
	author = {Icenhour, Casey and Lindsay, Alexander and Green, David and Martineau, Richard and Shannon, Steven},
	month = nov,
	year = {2018},
	note = {Report Number: 
INL/CON-18-45609-Rev000},
	file = {Full Text PDF:/Users/huff/Zotero/storage/DHCI4P7H/Icenhour et al. - 2018 - Elk A New MOOSE Framework Application for Radio-f.pdf:application/pdf},
}

@misc{slaughter_idaholabmagpie_2017,
	title = {idaholab/magpie},
	copyright = {LGPL-2.1},
	url = {https://www.osti.gov/biblio/1960129},
	abstract = {Mesoscale Atomistic Glue Program for Integrated Execution},
	urldate = {2024-06-04},
	publisher = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Slaughter, Andrew E. and Schunert, Sebastian and Carlsen, Robert and Peterson, John W. and Zhang, Yongfeng and Permann, Cody and Schwen, Daniel and Lindsay, Alex and Gaston, Derek},
	month = oct,
	year = {2017},
	doi = {10.11578/dc.20180424.4},
	note = {GitHub: https://github.com/idaholab/magpie},
	keywords = {fem, monte-carlo},
}

@inproceedings{shannon_plasma_2016,
	title = {Plasma {Simulation} in the {Multiphysics} {Object} {Oriented} {Simulation} {Environment} {MOOSE}},
	url = {https://ui.adsabs.harvard.edu/abs/2016APS..GECQR2002S},
	abstract = {MOOSE is an open source multiphysics solver developed by Idaho National Laboratory that is primarily used for the simulation of fission reactor systems; the framework is also well suited for the simulation of plasma systems given the development of appropriate modules not currently developed in the framework such as electromagnetic solvers, Boltzmann solvers, etc. It is structured for user development of application specific modules and is intended for both workstation level and high performance massively parallel environments. We have begun the development of plasma modules in the MOOSE environment and carried out preliminary simulation of the plasma/liquid interface to elucidate coupling mechanisms between these states using a fully coupled multiphysics model; these results agree well with PIC simulation of the same system and show strong response of plasma parameters with respect to electron reflection at the liquid surface. These results will be presented along with an overview of MOOSE and ongoing module development to extend capabilities to a broader set of research challenges in low temperature plasmas, with particular focus on RF and pulsed RF driven systems.},
	urldate = {2024-06-04},
	booktitle = {{APS} {Gaseous} {Electronics} {Conference} 2016},
	author = {Shannon, Steven and Lindsay, Alex and Graves, David and Icenhour, Casey and Peterson, David and White, Scott},
	month = sep,
	year = {2016},
	note = {Conference Name: APS Annual Gaseous Electronics Meeting Abstracts
ADS Bibcode: 2016APS..GECQR2002S},
	pages = {QR2.002},
}

@inproceedings{lindsay_fully_2016-1,
	title = {Fully coupled simulation of plasma-liquid systems: {Dependence} on interfacial properties},
	shorttitle = {Fully coupled simulation of plasma-liquid systems},
	url = {https://ieeexplore.ieee.org/abstract/document/7534078},
	doi = {10.1109/PLASMA.2016.7534078},
	abstract = {Summary form only given. Coupled plasma-liquid systems are at the heart of several burgeoning applications in low-temperature plasma science, including biomedicine, biological and chemical disinfection, agriculture, and others. In order to realize the full potential of these applications, the basic underlying physical and chemical phenomena must be understood. Recent modeling [1] and experimental [2] work have done much to elucidate system behavior but more questions remain, particularly in the interfacial region. The surface loss probability of gas phase electrons striking the interface, a critical parameter for many plasma simulations, is unknown; to date authors have generally assumed a value of unity, however there is no experimental evidence to either support or discourage this choice. The modeling work presented here explores the effects of varying key interfacial parameters. Two alternative interfacial models for electrons are considered: a kinetic one employing a surface loss probability, and a thermodynamic one in which the gas phase electron density is assumed to be in equilibrium with the liquid phase electron density with a ratio specified by a Henry's Law like coefficient (H). It is shown that if H is decreased from 106 ( H for hydrogen peroxide) to 102 ( H for hydroxyl radical), the gas phase electron density at the interface increases by three orders of magnitude. Moreover, if reflected electrons are still assumed to deposit their energy at the interface through collisions like vibrational excitation of surface molecules, then increasing reflection not only increases the density of gas phase electrons, but it also decreases the average energy of the electrons in the interfacial region. This could have significant impacts on both gas and liquid chemistry, e.g. the presence of a large number of colder electrons could lead to a large amount of electron attachment and production of negative ions in the near-interface region. The variability of key plasma variables like electron density and electron energy with respect to assumptions about the interface should motivate molecular scale simulations and/or new experimental diagnostics capable of probing the plasma in the near interface region.},
	urldate = {2024-06-04},
	booktitle = {2016 {IEEE} {International} {Conference} on {Plasma} {Science} ({ICOPS})},
	author = {Lindsay, Alex and Graves, David and Shannon, Steven},
	month = jun,
	year = {2016},
	pages = {1--1},
	file = {IEEE Xplore Abstract Record:/Users/huff/Zotero/storage/4LBNX8D6/7534078.html:text/html;IEEE Xplore Full Text PDF:/Users/huff/Zotero/storage/IGJGTUG2/Lindsay et al. - 2016 - Fully coupled simulation of plasma-liquid systems.pdf:application/pdf},
}

@inproceedings{noauthor_measurement_2015,
	address = {Honolulu, Hawaii},
	title = {Measurement of {OH} {Radical} in an {Atmospheric} {Plasma} {Generated} on {Water} {Surface}},
	url = {https://meetings.aps.org/Meeting/GEC15/Session/TF1.1},
	abstract = {Hyrdoxyl radicals are a well-known oxidizing agent that has many uses in the removal of contaminants from materials in both liquid and gas phases. To this end, an atmospheric plasma, operated at 162MHz, is used for the production of dissociated reactive species through plasma enhanced vaporization, ionization and the functionalization of liquid precursors via non-thermal plasma treatment. A coaxial source is used that has all components DC grounded allowing for the flow of water through the device creating a layer of water on the surface of the powered electrode. The plasma can be completely sustained through the evaporation of water from the electrode without the need for noble gases or any other feedgas. Air can also be flown through the device with little effect on OH densities but can be used to change the shape of the discharge at the exit of the device, which could be desirable for different applications. The emission spectrum of the discharge is completely dominated by the emissions of the hydroxyl radical. Spatially resolved absorption spectroscopy is performed using a broadband white light source that only requires a single pass through the plasma. OH concentrations have been calculated to be 1014-1016 cm-3.},
	urldate = {2024-06-04},
	booktitle = {68th {Annual} {Gaseous} {Electronics} {Conference}/9th {International} {Conference} on {Reactive} {Plasmas}/33rd {Symposium} on {Plasma} {Processing}},
	month = oct,
	year = {2015},
	file = {APS -68th Annual Gaseous Electronics Conference/9th International Conference on Reactive Plasmas/33rd Symposium on Plasma Processing - Event - Measurement of OH Radical in an Atmospheric Plasma Generated on Water Surface:/Users/huff/Zotero/storage/QMK8S7HW/TF1.html:text/html},
}

@inproceedings{lindsay_physical_2014,
	title = {Physical and chemical interactions at the interface between atmospheric pressure plasmas and aqueous solutions},
	url = {https://ui.adsabs.harvard.edu/abs/2014APS..GECLW2003L},
	abstract = {Transport and reactions of charged species, neutrals, and photons at the interface between plasmas and liquids must be better quantified. The work presented here combines theoretical and experimental investigations of conditions in the gas and liquid phases in proximity to the interface for various discharges. OES is used to determine rotational and vibrational temperatures of OH, NO, and N2+; the relationship between these temperatures that characterize the distribution of internal energy states and gas and electron kinetic temperatures is considered. The deviation of OH rotational states from equilibrium under high humidity conditions is also presented. In contradiction with findings of other groups, high energy rotational states appear to become underpopulated with increasing humidity. In the aqueous phase, concentrations of longer-lived species such as nitrate, nitrite, hydrogen peroxide, and ozone are determined using ion chromatography and colorimetric methods. Spin-traps and electron paramagnetic resonance (EPR) are investigated for characterization of short-lived aqueous radicals like OH, O2-, NO, and ONOO-. Finally, experimental results are compared to a numerical model which couples transport and reactions within and between the bulk gas and liquid phases.},
	urldate = {2024-06-04},
	booktitle = {{APS} {Gaseous} {Electronics} {Conference} 2014},
	author = {Lindsay, Alexander and Byrns, Brandon and Knappe, Detlef and Graves, David and Shannon, Steven},
	month = oct,
	year = {2014},
	note = {Conference Name: APS Annual Gaseous Electronics Meeting Abstracts
ADS Bibcode: 2014APS..GECLW2003L},
	pages = {LW2.003},
}

@inproceedings{lindsay_characterization_2014,
	title = {Characterization of atmospheric pressure rf discharges with aqueous plasma facing surfaces},
	url = {https://ieeexplore.ieee.org/abstract/document/7012279},
	doi = {10.1109/PLASMA.2014.7012279},
	abstract = {Summary form only given. Plasma modification of liquids has opened a broad range of new applications ranging from wound treatment to water purification to agricultural fertigation and herbicide. Two of the primary challenges facing systems designed to modify liquid chemistry through plasma treatment have been throughput and efficient introduction of liquid species in the active plasma region. In this presentation, we present novel pathways for both source scale up and liquid incorporation that can make plasma treatment of liquids more economically viable.},
	urldate = {2024-06-04},
	booktitle = {2014 {IEEE} 41st {International} {Conference} on {Plasma} {Sciences} ({ICOPS}) held with 2014 {IEEE} {International} {Conference} on {High}-{Power} {Particle} {Beams} ({BEAMS})},
	author = {Lindsay, Alex and Byrns, Brandon and Knappe, Detlef and Shannon, Steven},
	month = may,
	year = {2014},
	note = {ISSN: 0730-9244},
	keywords = {Chemistry, Electrodes, Liquids, Plasmas, Radio frequency, Surface discharges, Surface treatment},
	pages = {1--1},
	file = {IEEE Xplore Abstract Record:/Users/huff/Zotero/storage/8AH46C3L/7012279.html:text/html;IEEE Xplore Full Text PDF:/Users/huff/Zotero/storage/YZS9PL96/Lindsay et al. - 2014 - Characterization of atmospheric pressure rf discha.pdf:application/pdf},
}

@inproceedings{lindsay_atmospheric_2012,
	title = {Atmospheric {Pressure} {Glow} {Discharge} for {Point}-of-{Use} {Water} {Treatment}},
	url = {https://ui.adsabs.harvard.edu/abs/2012APS..GECDT3007L},
	abstract = {Treatment of biological and chemical contaminants is an area of growing global interest where atmospheric pressure plasmas can make a significant contribution. Addressing key challenges of volume processing and operational cost, a large volume 162 MHz coaxial air-plasma source has been developed.footnotetextByrns (2012) J. Phys. D: Appl. Phys. 45 (2012) 195204 Because of VHF ballasting effects, the electric discharge is maintained at a steady glow, allowing formation of critical non-equilibrium chemistry. High densities, ne = 10{\textasciicircum}11-10{\textasciicircum}12, have been recorded. The atmospheric nature of the device permits straightforward and efficient treatment of water samples. [H{\textasciicircum}+] concentrations in 150 milliliter tap water samples have been shown to increase by 10{\textasciicircum}5 after five minutes of discharge exposure. Recent literature has demonstrated that increasing acidity is strongly correlated with a solution's ability to deactivate microbial contaminants.footnotetextTraylor (2011) J. Phys. D: Appl. Phys. 44 (2011) 472001 The work presented here will explore the impact of treatment gas, system configuration, and power density on water disinfection and PFC abatement. An array of plasma diagnostics, including OES and electrical measurements, are combined with post-process water analysis, including GC-MS and QT analysis of coliform and E.coli bacteria. Development of volume processing atmospheric plasma disinfection methods offers promise for point-of-use treatments in developing areas of the world, potentially supplementing or replacing supply and weather-dependent disinfection methods.},
	urldate = {2024-06-04},
	booktitle = {American {Physical} {Society}, 65th {Annual} {Gaseous} {Electronics} {Conference}},
	author = {Lindsay, Alexander and Byrns, Brandon and Shannon, Steven and Knappe, Detlef},
	month = oct,
	year = {2012},
	note = {Conference Name: APS Annual Gaseous Electronics Meeting Abstracts
ADS Bibcode: 2012APS..GECDT3007L},
	pages = {DT3.007},
}

@inproceedings{byrns_vhf_2012-1,
	title = {{VHF} ballasting for high density atmospheric glow discharges},
	url = {https://ieeexplore.ieee.org/abstract/document/6383556},
	doi = {10.1109/PLASMA.2012.6383556},
	abstract = {Summary form only given. A major challenge in the production of large atmospheric glow plasmas is suppressing the transition to a thermal condition at higher power densities. One mechanism for forming a stable glow at moderate power densities is to sustain the plasma with a drive frequency where the glow exhibits ballasting characteristics that suppress the formation of thermally driven instabilities that lead to transition to a thermal discharge.},
	urldate = {2024-06-04},
	booktitle = {2012 {Abstracts} {IEEE} {International} {Conference} on {Plasma} {Science}},
	author = {Byrns, Brandon and Lindsay, Alex and Shannon, Steven},
	month = jul,
	year = {2012},
	note = {ISSN: 0730-9244},
	keywords = {Atmospheric modeling, Density measurement, Discharges (electric), Electronic ballasts, Glow discharges, Plasmas, Power system measurements},
	pages = {2P--169--2P--169},
	file = {IEEE Xplore Abstract Record:/Users/huff/Zotero/storage/EVA53B37/6383556.html:text/html;IEEE Xplore Full Text PDF:/Users/huff/Zotero/storage/KVNNRKHS/Byrns et al. - 2012 - VHF ballasting for high density atmospheric glow d.pdf:application/pdf},
}

@misc{dhulipala_seismic_2021,
	title = {Seismic fluid-structure interaction in tanks using an acoustic formulation: {A} verification and validation study},
	shorttitle = {Seismic fluid-structure interaction in tanks using an acoustic formulation},
	abstract = {Due to its computational efficiency and an ability to model complex geometries, an acoustic fluid-structure interaction (FSI) formulation is an attractive numerical approach for modeling fluid-filled tanks. However, few large-scale verification and validation (V\&V) studies exist that use acoustic FSI for seismic analysis while considering multiple response quantities and multi-directional seismic inputs. We present such a V\&V study performed using the Multiphysics Object-Oriented Simulation Environment (MOOSE). We first verify the acoustic FSI formulation using simple benchmark problems for which exact analytical solutions are available. Next, we verify acoustic FSI for a head-supported cylindrical tank partially filled with water and subjected to uni-directional shaking by comparing with analytical solutions, with which, the acoustic FSI results match closely. We validate acoustic FSI by comparing the simulation results with experimental data considering multi-directional seismic shaking of a base-supported cylindrical tank partially filled with water and subjected to peak ground accelerations of 0.1-1g. The acoustic FSI implementation in MOOSE satisfactorily predicts peak pressures and support moments recorded during the experiments. The comparisons also show that it might be challenging to predict the wave height at the fluid surface, given the complex surface wave responses, especially at more intense shaking. A comparison of simulation times showed that acoustic FSI is at least an order of magnitude faster than the arbitrary Lagrangian-Eulerian and incompressible computational fluid dynamics numerical methods. To demonstrate MOOSE's capabilities for handling large multiphysics numerical models , seismic FSI analysis is performed on a full-scale nuclear power plant building that houses a molten-salt reactor vessel.},
	author = {Dhulipala, Som and Bolisetti, Chandrakanth and Munday, Lynn and Hoffman, William and Yu, Ching-Ching and Mir, Faizan Ul Haq and Kong, Fande and Lindsay, Alexander and Whittaker, Andrew},
	month = aug,
	year = {2021},
	file = {Full Text PDF:/Users/huff/Zotero/storage/I8WCBYQV/Dhulipala et al. - 2021 - Seismic fluid-structure interaction in tanks using.pdf:application/pdf},
}

@inproceedings{lindsay_examining_2015,
	address = {Antwerp, Belgium},
	title = {Examining interfacial gradients in plasma-liquid systems through a coupled momentum, heat, and mass transport model},
	url = {https://www.ispc-conference.org/ispcproc/ispc22/O-6-1.pdf},
	abstract = {Transport phenomena at a plasma-liquid interface are investigated with a finiteelement model. Convection-induced evaporative cooling leads to factor of two changes in aqueous-phase concentrations relative to the case where convection-induced temperature effects are not considered. Additionally, aqueous concentrations of short-lived species like OH drop by as many as 9 orders of magnitude within 50 {\textmu}m of the interface.},
	language = {en},
	booktitle = {22nd {International} {Symposium} on {Plasma} {Chemistry}},
	author = {Lindsay, A and Anderson, C and Shannon, S and Graves, D B},
	month = jul,
	year = {2015},
	file = {Lindsay et al. - Examining interfacial gradients in plasma-liquid s.pdf:/Users/huff/Zotero/storage/GLU8E7GQ/Lindsay et al. - Examining interfacial gradients in plasma-liquid s.pdf:application/pdf},
}

@article{lindsay_examining_nodate,
	title = {Examining interfacial gradients in plasma-liquid systems through a coupled momentum, heat, and mass transport model},
	url = {https://www.ispc-conference.org/ispcproc/ispc22/O-6-1.pdf},
	urldate = {2024-06-04},
	author = {Lindsay, A. and Anderson, C. and Shannon, S. and Graves, D. B.},
	file = {Available Version (via Google Scholar):/Users/huff/Zotero/storage/XGTMJIPA/Lindsay et al. - Examining interfacial gradients in plasma-liquid s.pdf:application/pdf},
}

@phdthesis{agosta_enhanced_2023,
	type = {Thesis},
	title = {Enhanced method for the support of experiment safety analysis},
	copyright = {2023 Roberto E. Fairhurst Agosta},
	url = {https://hdl.handle.net/2142/122024},
	abstract = {Nuclear research reactors enable a wide range of applications and support the development of multiple fields, including energy production, isotope production, space discovery, among others. Research reactor safety analyses demonstrate the contribution of the operational procedures to the prevention of accidents, focusing mainly on the reactor core. These analyses rely on the assumption of heat being locally deposited in the core after shutdown. This work, however, is concerned with research reactor experiments, and it investigates more detailed methods targeting the specific reactor regions hosting the experiments.

Additionally, research reactor experiments require the development of individual experiment safety analyses, which due to the lack of a streamlined workflow becomes effort and time-consuming as well as error-prone. This thesis supports the development of safety analyses for research reactor experiments with the objective of streamlining the calculation procedure as well as accelerating it. The methodology presented here calculates the delayed heating in experiments, generates the volumetric heat source term for thermal-fluids calculations, solves the experiment temperature evolution during a channel draining event, and determines if the event leads to a radioactive material release. Moreover, this work examines methods to accelerate the calculation, which include the creation of a generic material irradiation database and data-based modeling.

This thesis starts with a literature survey summarizing previous work relevant to delayed heating calculations, transport/depletion solvers, and machine learning applied to nuclear engineering. The conclusions of the survey guide the choice of methods for the delayed heating calculation and the choice of machine learning algorithms for the data-based modeling.

The following chapters focus on the calculation workflows. This thesis establishes a delayed heating calculation workflow based on the formal three-step method that builds on top of the MCNP-ORIGEN Activation Automation (MOAA) tool. This workflow is demonstrated and verified with several exercises, which also ease the workflow visualization. The workflow is also demonstrated in two full-size research reactors, for which the heat in the structures and an experiment are calculated.

A simple modification of the delayed heating calculation workflow generates a shutdown dose rate calculation workflow as a value-added. This calculation workflow helps guide the post-irradiation examination (PIE) of experiments and helps prevent the unnecessary exposure of personnel and surrounding equipment. The calculation workflow is demonstrated for a Tristructural Isotropic (TRISO)-fueled experiment which highlights the applicability of this workflow to more complex geometries, such as High-Temperature Gas-Cooled Reactors (HTGRs).

When focusing on the acceleration of the calculations, this thesis proposes the generic material irradiation database method. This method relies on the delayed heating calculation workflow to obtain the heat produced in experiments of individual chemical elements and through their combination calculate the heat produced in experiments of arbitrary material composition. This thesis verifies this method by studying a vast range of materials that could be used in a research reactor experiment.

Moreover, this thesis investigates the applicability of data-based modeling to predict the outcome of the most thermally challenging accident in an experiment, a channel draining event. The data preparation process and several machine learning algorithms are described before studying a simplified model. Several useful conclusions are drawn with the simplified model before scaling it up, with some minor modifications, to a full-size reactor experiment.

Finally, this thesis wraps up with the conclusions from all the previous calculations. Overall, the results presented in this thesis meet this thesis{\textquoteright} objectives and prove that the proposed methodology decreases the computational expense and enables quick calculations supporting research reactor experiments.},
	urldate = {2024-06-04},
	school = {University of Illinois at Urbana-Champaign},
	author = {Agosta, Fairhurst and Enrique, Roberto},
	month = nov,
	year = {2023},
	file = {Full Text PDF:/Users/huff/Zotero/storage/H4NXI5ME/Agosta and Enrique - 2023 - Enhanced method for the support of experiment safe.pdf:application/pdf},
}

@inproceedings{fairhurst-agosta_development_2022,
	series = {Proceedings of the {International} {Conference} on {Physics} of {Reactors}, {PHYSOR} 2022},
	title = {Development of the {MCNP}-{ORIGEN} {Activation} {Automation} tool: 2022 {International} {Conference} on {Physics} of {Reactors}, {PHYSOR} 2022},
	shorttitle = {Development of the {MCNP}-{ORIGEN} {Activation} {Automation} tool},
	url = {http://www.scopus.com/inward/record.url?scp=85179784185&partnerID=8YFLogxK},
	doi = {10.13182/PHYSOR22-37565},
	abstract = {This paper introduces the MCNP-ORIGEN Activation Automation tool for streamlining the calculation of experiment source terms. This tool couples the Monte Carlo radiation-transport solver, MCNP [1], to the depletion tool, ORIGEN-S [2]. To showcase its current capabilities, this paper presents an activation analysis exercise, which is conducted with Serpent, and the results are compared. These studies highlight the discrepancies between how the different tools handle nuclear data. Finally, the results underscore multiple areas of possible improvement.},
	urldate = {2024-06-04},
	booktitle = {Proceedings of the {International} {Conference} on {Physics} of {Reactors}, {PHYSOR} 2022},
	author = {Fairhurst-Agosta, Roberto E. and Carter, Austin L. and Peterson-Droogh, Joshua L.},
	year = {2022},
	note = {Publisher: American Nuclear Society},
	keywords = {Activation, Irradiation, MCNP, MOAA, ORIGEN},
	pages = {1923--1932},
	annote = {Publisher Copyright:{\textcopyright} 2022 Proceedings of the International Conference on Physics of Reactors, PHYSOR 2022. All Rights Reserved.},
}

@inproceedings{fairhurst-agosta_database_2022,
	title = {Database {Construction} for {Nuclear} {Heating} {Calculations}},
	volume = {127},
	doi = {10.13182/T127-39622},
	language = {English},
	booktitle = {Transactions of the {American} {Nuclear} {Society}},
	author = {Fairhurst-Agosta, R.E. and Kozlowski, T.},
	year = {2022},
	note = {ISSN: 0003-018X
Issue: 1},
	pages = {352--355},
	annote = {Cited By :1},
	file = {Snapshot:/Users/huff/Zotero/storage/VTTVVLGV/display.html:text/html},
}

@techreport{fairhurst_agosta_nuclear_2022,
	title = {Nuclear {Quality} {Assurance} {Certification} of the {MCNP}-{ORIGEN} {Activation} {Automation} tool},
	url = {https://www.osti.gov/biblio/1985492},
	abstract = {The MCNP-ORIGEN Activation Automation (MOAA) tool couples MCNP and ORIGEN-S, allowing to support ATR and TREAT experiments by predicting their composition and activity before their irradiation takes place. MOAA is developed and maintained by the Irradiation Experiment Neutronics Analysis group (C-150) at INL. This poster presents the motivation behind the development of MOAA, its main workflow, as well as the software quality assurance (SQA) efforts required by LWP-13620, "Managing Information Technology Assets."},
	language = {English},
	number = {INL/EXP-22-68480-Rev000},
	urldate = {2024-06-04},
	institution = {Idaho National Laboratory (INL), Idaho Falls, ID (United States)},
	author = {Fairhurst Agosta, Roberto E. and Carter, Austin L. and Peterson-Droogh, Joshua L.},
	month = aug,
	year = {2022},
	file = {Full Text PDF:/Users/huff/Zotero/storage/23C2E7G2/Fairhurst Agosta et al. - 2022 - Nuclear Quality Assurance Certification of the MCN.pdf:application/pdf},
}

@article{fairhurst_agosta_shutdown_2023,
	title = {Shutdown dose rate ... {\textbar} {Nuclear} {Science} and {Technology} {Open} {Research}},
	url = {https://nstopenresearch.org/articles/1-20},
	doi = {https://doi.org/10.12688/nuclscitechnolopenres.17447.1},
	abstract = {Background
High-temperature gas-cooled reactors (HTGRs) have many distinct features from the current light water reactor (LWR) fleet, and potential decommissioning strategies should take them into consideration. The proper characterization of the shutdown dose rates can establish a suitable strategy.

Methods
This article introduces a new shutdown dose rate calculation capability that relies on the MCNP-ORIGEN activation automation tool and the MCNP repeated structures to explicitly model the TRistructural ISOtropic (TRISO) particles as decay radiation sources.

Results
Three exercises are conducted with this capability, and their results discussed. The first two exercises verify and demonstrate the workflow. The third exercise proposes a decommissioning strategy for a high-temperature gas-cooled microreactor and studies its feasibility from the shutdown dose rate standpoint. The calculations yield a dose rate map above at the reactor citadel after a three month cool-down, showing values above 40 mSv/h.

Conclusions
The findings imply that the decommissioning strategy based on placing the reactor in a safe shutdown state and allowing it to cool down for three months before removing various components and extracting the fuel assemblies, may not be sufficient to minimize unnecessary exposure of personnel.},
	urldate = {2024-06-04},
	journal = {Sushil C. Jain Research from ANS Student Conferences Collection},
	author = {Fairhurst Agosta, Roberto and Kozlowksi, Tomasz},
	month = nov,
	year = {2023},
	file = {Shutdown dose rate ... | Nuclear Science and Technology Open Research:/Users/huff/Zotero/storage/GKPL6DER/1-20.html:text/html},
}