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Fix potential bug with nuclide densities in Results.export_to_materials

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This commit is contained in:
Paul Romano 2022-08-10 23:12:01 -05:00
parent 1be8941e35
commit f9b2c21d59
1 changed files with 9 additions and 0 deletions
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9
openmc/deplete/results.py
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@ -417,7 +417,16 @@ class Results(list):
mat_id = str(mat.id)
if mat_id in result.mat_to_ind:
mat.volume = result.volume[mat_id]
# Change density of all nuclides in material to atom/b-cm
atoms_per_barn_cm = mat.get_nuclide_atom_densities()
for nuc, value in atoms_per_barn_cm.items():
mat.remove_nuclide(nuc)
mat.add_nuclide(nuc, value)
mat.set_density('sum')
# For nuclides in chain that have cross sections, replace
# density in original material with new density from results
for nuc in result.nuc_to_ind:
if nuc not in available_cross_sections:
continue