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Allow IncidentNeutron.from_endf to work on heatr output files

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Paul Romano 2019-09-11 15:38:59 -05:00
parent 251ecba60b
commit d630047f4c
1 changed files with 4 additions and 3 deletions
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7
openmc/data/neutron.py
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@ -777,9 +777,10 @@ class IncidentNeutron(EqualityMixin):
for mt, rx in data.reactions.items():
if mt in (19, 20, 21, 38):
if (5, mt) not in ev.section:
neutron = data.reactions[18].products[0]
rx.products[0].applicability = neutron.applicability
rx.products[0].distribution = neutron.distribution
if rx.products:
neutron = data.reactions[18].products[0]
rx.products[0].applicability = neutron.applicability
rx.products[0].distribution = neutron.distribution
# Read fission energy release (requires that we already know nu for
# fission)