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check if nuclide is fissionable in eigenvalue tally
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ilhamv committed Nov 10, 2024
1 parent bd510fe commit c3c3e3b
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2 changes: 2 additions & 0 deletions mcdc/kernel.py
Original file line number Diff line number Diff line change
Expand Up @@ -2126,6 +2126,8 @@ def eigenvalue_tally(P_arr, distance, mcdc):
for i in range(material["N_nuclide"]):
ID_nuclide = material["nuclide_IDs"][i]
nuclide = mcdc["nuclides"][ID_nuclide]
if not nuclide["fissionable"]:
continue
for j in range(J):
nu_d = get_nu_group(NU_FISSION_DELAYED, nuclide, E, j)
decay = nuclide["ce_decay"][j]
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