From 510711e92f6045fdf6928c149db8631a4c4d7dcd Mon Sep 17 00:00:00 2001 From: "wbinventor@gmail.com" Date: Sun, 6 Dec 2015 19:58:19 -0500 Subject: [PATCH 1/2] Now store keff as an attribute in MGXS Library class --- openmc/mgxs/library.py | 10 ++++++++++ 1 file changed, 10 insertions(+) diff --git a/openmc/mgxs/library.py b/openmc/mgxs/library.py index 0bf9732549..6845abf20e 100644 --- a/openmc/mgxs/library.py +++ b/openmc/mgxs/library.py @@ -67,6 +67,9 @@ class Library(object): sp_filename : str The filename of the statepoint with tally data used to the compute cross sections + keff : Real or None + The combined keff from the statepoint file with tally data used to + compute cross sections name : str, optional Name of the multi-group cross section library. Used as a label to identify tallies in OpenMC 'tallies.xml' file. @@ -88,6 +91,7 @@ class Library(object): self._tally_trigger = None self._all_mgxs = OrderedDict() self._sp_filename = None + self._keff = None self.name = name self.openmc_geometry = openmc_geometry @@ -114,6 +118,7 @@ class Library(object): clone._tally_trigger = copy.deepcopy(self.tally_trigger, memo) clone._all_mgxs = self.all_mgxs clone._sp_filename = self._sp_filename + clone._keff = self._keff clone._all_mgxs = OrderedDict() for domain in self.domains: @@ -199,6 +204,10 @@ class Library(object): def sp_filename(self): return self._sp_filename + @property + def keff(self): + return self._keff + @openmc_geometry.setter def openmc_geometry(self, openmc_geometry): cv.check_type('openmc_geometry', openmc_geometry, openmc.Geometry) @@ -363,6 +372,7 @@ class Library(object): self._sp_filename = statepoint._f.filename self._openmc_geometry = statepoint.summary.openmc_geometry + self._keff = statepoint.k_combined[0] # Load tallies for each MGXS for each domain and mgxs type for domain in self.domains: From e55f9fb3eea1a35a6acafe7929a9ddad6e263cf4 Mon Sep 17 00:00:00 2001 From: "wbinventor@gmail.com" Date: Mon, 7 Dec 2015 08:48:41 -0500 Subject: [PATCH 2/2] 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: