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Don't append to Tally filters on FY helpers

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As pointed out in
https://github.com/openmc-dev/openmc/pull/1313/files#r315844775,
appending to Tally.filters does not propagate to the C++ side.
New filter lists are created using the previous lists, and
then passed onto to the Tally.filters setter.
This commit is contained in:
Andrew Johnson 2019-08-21 09:45:09 -05:00
parent 1d046ab4f6
commit 6735657cb3
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1 changed files with 10 additions and 12 deletions
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22
openmc/deplete/helpers.py
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@ -378,9 +378,9 @@ class FissionYieldCutoffHelper(TalliedFissionYieldHelper):
in parallel mode.
"""
super().generate_tallies(materials, mat_indexes)
energy_filter = EnergyFilter()
energy_filter.bins = (0.0, self._cutoff, self._upper_energy)
self._fission_rate_tally.filters.append(energy_filter)
energy_filter = EnergyFilter(bins=[0.0, self._cutoff, self._upper_energy])
self._fission_rate_tally.filters = (
self._fission_rate_tally.filters + [energy_filter])
def unpack(self):
"""Obtain fast and thermal fission fractions from tally"""
@ -510,18 +510,16 @@ class AveragedFissionYieldHelper(TalliedFissionYieldHelper):
"""
super().generate_tallies(materials, mat_indexes)
fission_tally = self._fission_rate_tally
filters = fission_tally.filters
ene_filter = EnergyFilter(bins=[0, self._upper_energy])
fission_tally.filters = filters + [ene_filter]
func_filter = EnergyFunctionFilter()
func_filter.set_data((0, self._upper_energy), (0, self._upper_energy))
weighted_tally = Tally()
weighted_tally.filters = fission_tally.filters
weighted_tally.scores = ['fission']
ene_bin = EnergyFilter()
ene_bin.bins = (0, self._upper_energy)
fission_tally.filters.append(ene_bin)
ene_filter = EnergyFunctionFilter()
ene_filter.set_data((0, self._upper_energy), (0, self._upper_energy))
weighted_tally.filters.append(ene_filter)
weighted_tally.filters = filters + [func_filter]
self._weighted_tally = weighted_tally
def update_tally_nuclides(self, nuclides):