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Now only store keff in MGXS Library for eigenvalue calculations

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wbinventor@gmail.com 2015-12-07 08:48:41 -05:00
parent 510711e92f
commit e55f9fb3ee
1 changed files with 4 additions and 2 deletions
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6
openmc/mgxs/library.py
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@ -69,7 +69,7 @@ class Library(object):
compute cross sections
keff : Real or None
The combined keff from the statepoint file with tally data used to
compute cross sections
compute cross sections (for eigenvalue calculations only)
name : str, optional
Name of the multi-group cross section library. Used as a label to
identify tallies in OpenMC 'tallies.xml' file.
@ -372,7 +372,9 @@ class Library(object):
self._sp_filename = statepoint._f.filename
self._openmc_geometry = statepoint.summary.openmc_geometry
self._keff = statepoint.k_combined[0]
if statepoint.run_mode == 'k-effective':
self._keff = statepoint.k_combined[0]
# Load tallies for each MGXS for each domain and mgxs type
for domain in self.domains: