diff --git a/README.md b/README.md
index 9271b7c..7db130c 100644
--- a/README.md
+++ b/README.md
@@ -31,127 +31,35 @@ Below are some basic examples, for more examples see the [examples folder](https
 
 ## Plot of energy distribution of the source
 
-```python
-import openmc
-import openmc_source_plotter  # extends openmc.IndependentSource with plotting functions
-
-# initialises a new source object
-my_source = openmc.IndependentSource()
-
-# sets the energy distribution to a muir distribution neutrons for DT fusion neutrons
-my_source.energy = openmc.stats.muir(e0=14080000.0, m_rat=5.0, kt=20000.0)
-
-# plots the particle energy distribution
-plot = my_source.plot_source_energy(n_samples=2000)
-
-plot.show()
-```
+:link:[Link](https://github.com/fusion-energy/openmc_source_plotter/blob/main/examples/example_plot_source_energy.py) to example script.
 
 ![openmc particle source energy plot](https://user-images.githubusercontent.com/8583900/143615694-a3578115-f8a2-4971-bf26-458177b4f113.png)
 
 ## Plot of energy distribution of two sources
 
-```python
-import openmc
-import openmc_source_plotter  # extends openmc.IndependentSource with plotting functions
-
-# initialises a new source object
-my_dt_source = openmc.IndependentSource()
-
-# sets the energy distribution to a muir distribution DT neutrons
-my_dt_source.energy = openmc.stats.muir(e0=14080000.0, m_rat=5.0, kt=20000.0)
-
-# initialises a new source object
-my_dd_source = openmc.IndependentSource()
-# sets the energy distribution to a muir distribution DD neutrons
-my_dd_source.energy = openmc.stats.muir(e0=2080000.0, m_rat=2.0, kt=20000.0)
-
-# plots the particle energy distribution by building on the first plot
-figure1 = my_dd_source.plot_source_energy(n_samples=10000)
-figure2 = my_dt_source.plot_source_energy(figure=figure1, n_samples=10000)
-
-figure2.show()
-```
+:link:[Link](https://github.com/fusion-energy/openmc_source_plotter/blob/main/examples/example_plot_two_source_energies.py) to example script.
 
 ![openmc particle source energy plot](https://user-images.githubusercontent.com/8583900/151376414-fb1555eb-61d1-4c82-bc4d-a05f62819c5d.png)
 
 ## Plot direction of particles
 
-```python
-import openmc
-import openmc_source_plotter  # extends openmc.IndependentSource with plotting functions
-
-# initializes a new source object
-my_source = openmc.IndependentSource()
-
-# sets the direction to isotropic
-my_source.angle = openmc.stats.Isotropic()
-
-# plots the particle energy distribution
-plot = my_source.plot_source_direction(n_samples=200)
-
-plot.show()
-```
+:link:[Link](https://github.com/fusion-energy/openmc_source_plotter/blob/main/examples/example_plot_source_direction.py) to example script.
 
 ![openmc particle source direction plot](https://user-images.githubusercontent.com/8583900/143615706-3b3a8467-0233-42d6-a66c-d536c80a01d8.png)
 
 
-<!-- ## Plot gamma spectrum of particles
-
-```python
-import openmc
-import openmc_source_plotter  # adds plot_gamma_emission plot to materials
-
-
-openmc.config["chain_file"] = "chain-endf.xml"
-
-my_material = openmc.Material()
-my_material.add_nuclide("Xe135", 1e-12)
-my_material.add_nuclide("U235", 1)
-my_material.add_nuclide("U238", 1)
-my_material.add_nuclide("Co60", 1e-9)
-my_material.volume = 1  # must be set so number of atoms can be found
-
-# adds labels to the most active 3 gamma energies
-plt = my_material.plot_gamma_emission(label_top=3)
-plt.xscale("log")  # modify axis from default settings
-plt.savefig("gamma_spec.png")
-```
-
-![openmc gamma spectrum](https://user-images.githubusercontent.com/8583900/228280129-b8160e18-9ca9-4b20-a4e1-d2948908daf6.png) -->
-
 ## Plot position of particles
 
-```python
-import openmc
-import openmc_source_plotter  # extends openmc.IndependentSource with plotting functions
-
-# initialises a new source object
-my_source = openmc.IndependentSource()
-
-# the distribution of radius is just a single value
-radius = openmc.stats.Discrete([10], [1])
+:link:[Link](https://github.com/fusion-energy/openmc_source_plotter/blob/main/examples/example_plot_source_position.py) to example script.
 
-# the distribution of source z values is just a single value
-z_values = openmc.stats.Discrete([0], [1])
 
-# the distribution of source azimuthal angles
-# values is a uniform distribution between 0 and 2 Pi
-angle = openmc.stats.Uniform(a=0.0, b=2 * 3.14159265359)
-
-# this makes the ring source using the three distributions and a radius
-my_source.space = openmc.stats.CylindricalIndependent(
-    r=radius, phi=angle, z=z_values, origin=(0.0, 0.0, 0.0)
-)
+![openmc particle source position plot](https://user-images.githubusercontent.com/8583900/179424915-bee56a87-6214-46ef-8625-92b8f4cbd1b3.png)
 
-# plots the particle energy distribution
-plot = my_source.plot_source_position()
+## Plot labeled gamma lines from material
 
-plot.show()
-```
+:link:[Link](https://github.com/fusion-energy/openmc_source_plotter/blob/main/examples/example_gamma_spec_plot.py) to example script.
 
-
-![openmc particle source position plot](https://user-images.githubusercontent.com/8583900/179424915-bee56a87-6214-46ef-8625-92b8f4cbd1b3.png)
+![gamma spec with labels](examples/gamma_spec.png)
 
 
 ## Extract particle objects
diff --git a/examples/example_gamma_spec_plot.py b/examples/example_gamma_spec_plot.py
index 1fdcaf2..f87ea70 100644
--- a/examples/example_gamma_spec_plot.py
+++ b/examples/example_gamma_spec_plot.py
@@ -1,8 +1,8 @@
 import openmc
 import openmc_source_plotter  # adds plot_gamma_emission plot to materials
 
-
-openmc.config["chain_file"] = "chain-endf.xml"
+# this path will need changing to point to your chain file
+# openmc.config["chain_file"] = "chain-endf.xml"
 
 my_material = openmc.Material()
 my_material.add_nuclide("Xe135", 1e-12)
diff --git a/examples/gamma_spec.png b/examples/gamma_spec.png
new file mode 100644
index 0000000..94d00ce
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