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Allow hybrid rx helper to work with no reactions specified

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This commit is contained in:
Paul Romano 2020-09-03 10:11:04 -05:00
parent 96a66789b1
commit 52bee7bee2
1 changed files with 14 additions and 12 deletions
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26
openmc/deplete/helpers.py
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@ -230,16 +230,16 @@ class HybridReactionHelper(ReactionRateHelper):
All nuclides with desired reaction rates.
"""
def __init__(self, n_nucs, n_reacts, energies, reactions, nuclides=None):
def __init__(self, n_nucs, n_reacts, energies, reactions=None, nuclides=None):
super().__init__(n_nucs, n_reacts)
self._energies = asarray(energies)
self._reactions_direct = list(reactions)
self._reactions_direct = list(reactions) if reactions is not None else []
self._nuclides_direct = list(nuclides) if nuclides is not None else None
@ReactionRateHelper.nuclides.setter
def nuclides(self, nuclides):
ReactionRateHelper.nuclides.fset(self, nuclides)
if self._nuclides_direct is None:
if self._reactions_direct and self._nuclides_direct is None:
self._rate_tally.nuclides = nuclides
def generate_tallies(self, materials, scores):
@ -275,12 +275,13 @@ class HybridReactionHelper(ReactionRateHelper):
self._flux_tally.scores = ['flux']
# Create reaction rate tally
self._rate_tally = Tally()
self._rate_tally.writable = False
self._rate_tally.scores = self._reactions_direct
self._rate_tally.filters = [MaterialFilter(materials)]
if self._nuclides_direct is not None:
self._rate_tally.nuclides = self._nuclides_direct
if self._reactions_direct:
self._rate_tally = Tally()
self._rate_tally.writable = False
self._rate_tally.scores = self._reactions_direct
self._rate_tally.filters = [MaterialFilter(materials)]
if self._nuclides_direct is not None:
self._rate_tally.nuclides = self._nuclides_direct
def get_material_rates(self, mat_index, nuc_index, react_index):
"""Return an array of reaction rates for a material
@ -310,9 +311,10 @@ class HybridReactionHelper(ReactionRateHelper):
flux = mean_value[mat_index]
# Get direct reaction rates
nuclides_direct = self._rate_tally.nuclides
shape = (len(nuclides_direct), len(self._reactions_direct))
rx_rates = self._rate_tally.mean[mat_index].reshape(shape)
if self._reactions_direct:
nuclides_direct = self._rate_tally.nuclides
shape = (len(nuclides_direct), len(self._reactions_direct))
rx_rates = self._rate_tally.mean[mat_index].reshape(shape)
mat = self._materials[mat_index]