crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-27 05:35:49 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions

Revised order of operations for consistent scattering matrix calculation to work with multiple nuclides

Browse source
This commit is contained in:
Will Boyd 2017-04-10 17:27:28 -04:00
parent e9dfad8519
commit d359909aa8
1 changed files with 4 additions and 7 deletions
Download patch file Download diff file Expand all files Collapse all files

11
openmc/mgxs/mgxs.py
View file

@ -3956,10 +3956,6 @@ class ScatterMatrixXS(MatrixMGXS):
self._xs_tally = MGXS.xs_tally.fget(self)
else:
# Compute groupwise scattering cross section
self._xs_tally = self.tallies['scatter'] / \
self.tallies['flux (tracklength)']
# Compute scattering probability matrix
energyout_bins = [self.energy_groups.get_group_bounds(i)
for i in range(self.num_groups, 0, -1)]
@ -3969,7 +3965,6 @@ class ScatterMatrixXS(MatrixMGXS):
norm = self.tallies[tally_key].get_slice(scores=['scatter-0'])
norm = norm.summation(
filter_type=openmc.EnergyoutFilter, filter_bins=energyout_bins)
# Remove the AggregateFilter summed across energyout bins
norm._filters = norm._filters[:2]
@ -3990,8 +3985,10 @@ class ScatterMatrixXS(MatrixMGXS):
# Remove the AggregateFilter summed across mu bins
norm._filters = norm._filters[:2]
# Multiply by the group-to-group probability matrix
self._xs_tally *= (self.tallies[tally_key] / norm)
# Compute groupwise scattering cross section
self._xs_tally = \
self.tallies['scatter'] * self.tallies[tally_key] / norm
self._xs_tally /= self.tallies['flux (tracklength)']
# Multiply by the multiplicity matrix
if self.nu: