From e55f9fb3eea1a35a6acafe7929a9ddad6e263cf4 Mon Sep 17 00:00:00 2001 From: "wbinventor@gmail.com" Date: Mon, 7 Dec 2015 08:48:41 -0500 Subject: [PATCH] Now only store keff in MGXS Library for eigenvalue calculations --- openmc/mgxs/library.py | 6 ++++-- 1 file changed, 4 insertions(+), 2 deletions(-) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 6845abf20e..ebf4050773 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -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: