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Improve logic for determining redundant reactions

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This commit is contained in:
Paul Romano 2018-11-12 15:19:04 -06:00
parent 62edb23fd3
commit 7c3c0bb731
1 changed files with 10 additions and 23 deletions
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33
openmc/data/neutron.py
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@ -375,15 +375,13 @@ class IncidentNeutron(EqualityMixin):
self.energy['0K'] = x
self[2].xs['0K'] = Tabulated1D(x, y)
def get_reaction_components(self, mt, exclude_self=False):
def get_reaction_components(self, mt):
"""Determine what reactions make up redundant reaction.
Parameters
----------
mt : int
ENDF MT number of the reaction to find components of.
exclude_self : bool
Whether to exclude the original MT number when finding components
Returns
-------
@ -392,24 +390,14 @@ class IncidentNeutron(EqualityMixin):
have cross sections provided.
"""
if mt in self.reactions and not exclude_self:
return [mt]
elif mt in SUM_RULES:
mts = SUM_RULES[mt]
mts = []
if mt in SUM_RULES:
for mt_i in SUM_RULES[mt]:
mts += self.get_reaction_components(mt_i)
if mts:
return mts
else:
return []
complete = False
while not complete:
new_mts = []
complete = True
for i, mt_i in enumerate(mts):
if mt_i in self.reactions:
new_mts.append(mt_i)
elif mt_i in SUM_RULES:
new_mts += SUM_RULES[mt_i]
complete = False
mts = new_mts
return mts
return [mt] if mt in self else []
def export_to_hdf5(self, path, mode='a', libver='earliest'):
"""Export incident neutron data to an HDF5 file.
@ -700,12 +688,11 @@ class IncidentNeutron(EqualityMixin):
rx = data._get_redundant_reaction(mt, mts)
data.reactions[mt] = rx
# Make sure redundant cross sections that are present in an ACE file get
# marked as such
for rx in data:
mts = data.get_reaction_components(rx.mt, exclude_self=True)
if mts:
mts = data.get_reaction_components(rx.mt)
if mts != [rx.mt]:
rx.redundant = True
# Read unresolved resonance probability tables