crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 14:15:42 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Now use MGXS._tallies attribute directly instead of using super to call it in base MGXS class

Browse source
This commit is contained in:
Will Boyd 2015-11-02 16:48:41 -05:00
parent 90de395f53
commit c4009ee294
1 changed files with 22 additions and 22 deletions
Download patch file Download diff file Expand all files Collapse all files

44
openmc/mgxs/mgxs.py
View file

@ -1286,7 +1286,7 @@ class TotalXS(MGXS):
"""
# Instantiate tallies if they do not exist
if super(TotalXS, self).tallies is None:
if self._tallies is None:
# Create a list of scores for each Tally to be created
scores = ['flux', 'total']
@ -1301,7 +1301,7 @@ class TotalXS(MGXS):
# Initialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(TotalXS, self).tallies
return self._tallies
def compute_xs(self):
"""Computes the multi-group total cross sections using OpenMC
@ -1332,7 +1332,7 @@ class TransportXS(MGXS):
"""
# Instantiate tallies if they do not exist
if super(TransportXS, self).tallies is None:
if self._tallies is None:
# Create a list of scores for each Tally to be created
scores = ['flux', 'total', 'scatter-P1']
@ -1348,7 +1348,7 @@ class TransportXS(MGXS):
# Initialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(TransportXS, self).tallies
return self._tallies
def compute_xs(self):
"""Computes the multi-group transport cross sections using OpenMC
@ -1384,7 +1384,7 @@ class AbsorptionXS(MGXS):
"""
# Instantiate tallies if they do not exist
if super(AbsorptionXS, self).tallies is None:
if self._tallies is None:
# Create a list of scores for each Tally to be created
scores = ['flux', 'absorption']
@ -1399,7 +1399,7 @@ class AbsorptionXS(MGXS):
# Initialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(AbsorptionXS, self).tallies
return self._tallies
def compute_xs(self):
"""Computes the multi-group absorption cross sections using OpenMC
@ -1436,7 +1436,7 @@ class CaptureXS(MGXS):
"""
# Instantiate tallies if they do not exist
if super(CaptureXS, self).tallies is None:
if self._tallies is None:
# Create a list of scores for each Tally to be created
scores = ['flux', 'absorption', 'fission']
@ -1451,7 +1451,7 @@ class CaptureXS(MGXS):
# Initialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(CaptureXS, self).tallies
return self._tallies
def compute_xs(self):
"""Computes the multi-group capture cross sections using OpenMC
@ -1482,7 +1482,7 @@ class FissionXS(MGXS):
"""
# Instantiate tallies if they do not exist
if super(FissionXS, self).tallies is None:
if self._tallies is None:
# Create a list of scores for each Tally to be created
scores = ['flux', 'fission']
@ -1497,7 +1497,7 @@ class FissionXS(MGXS):
# Initialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(FissionXS, self).tallies
return self._tallies
def compute_xs(self):
"""Computes the multi-group fission cross sections using OpenMC
@ -1527,7 +1527,7 @@ class NuFissionXS(MGXS):
"""
# Instantiate tallies if they do not exist
if super(NuFissionXS, self).tallies is None:
if self._tallies is None:
# Create a list of scores for each Tally to be created
scores = ['flux', 'nu-fission']
@ -1542,7 +1542,7 @@ class NuFissionXS(MGXS):
# Initialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(NuFissionXS, self).tallies
return self._tallies
def compute_xs(self):
"""Computes the multi-group nu-fission cross sections using OpenMC
@ -1572,7 +1572,7 @@ class ScatterXS(MGXS):
"""
# Instantiate tallies if they do not exist
if super(ScatterXS, self).tallies is None:
if self._tallies is None:
# Create a list of scores for each Tally to be created
scores = ['flux', 'scatter']
@ -1587,7 +1587,7 @@ class ScatterXS(MGXS):
# Intialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(ScatterXS, self).tallies
return self._tallies
def compute_xs(self):
"""Computes the scattering multi-group cross sections using
@ -1617,7 +1617,7 @@ class NuScatterXS(MGXS):
"""
# Instantiate tallies if they do not exist
if super(NuScatterXS, self).tallies is None:
if self._tallies is None:
# Create a list of scores for each Tally to be created
scores = ['flux', 'nu-scatter']
@ -1632,7 +1632,7 @@ class NuScatterXS(MGXS):
# Initialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(NuScatterXS, self).tallies
return self._tallies
def compute_xs(self):
"""Computes the nu-scattering multi-group cross section using OpenMC
@ -1679,7 +1679,7 @@ class ScatterMatrixXS(MGXS):
"""
# Instantiate tallies if they do not exist
if super(ScatterMatrixXS, self).tallies is None:
if self._tallies is None:
group_edges = self.energy_groups.group_edges
energy = openmc.Filter('energy', group_edges)
@ -1699,7 +1699,7 @@ class ScatterMatrixXS(MGXS):
# Initialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(ScatterMatrixXS, self).tallies
return self._tallies
@correction.setter
def correction(self, correction):
@ -1989,7 +1989,7 @@ class NuScatterMatrixXS(ScatterMatrixXS):
"""
# Instantiate tallies if they do not exist
if super(ScatterMatrixXS, self).tallies is None:
if self._tallies is None:
# Create the non-domain specific Filters for the Tallies
group_edges = self.energy_groups.group_edges
@ -2011,7 +2011,7 @@ class NuScatterMatrixXS(ScatterMatrixXS):
# Intialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(ScatterMatrixXS, self).tallies
return self._tallies
class Chi(MGXS):
"""The fission spectrum."""
@ -2032,7 +2032,7 @@ class Chi(MGXS):
"""
# Instantiate tallies if they do not exist
if super(Chi, self).tallies is None:
if self._tallies is None:
# Create a list of scores for each Tally to be created
scores = ['nu-fission', 'nu-fission']
@ -2048,7 +2048,7 @@ class Chi(MGXS):
# Intialize the Tallies
self.create_tallies(scores, filters, keys, estimator)
return super(Chi, self).tallies
return self._tallies
def compute_xs(self):
"""Computes chi fission spectrum using OpenMC tally arithmetic."""