crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 06:05:58 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

updated setting of delayed groups in mgxs tests

Browse source
This commit is contained in:
Sam Shaner 2016-10-19 11:58:32 -04:00
parent e28f71a27e
commit 5f750f3976
6 changed files with 8 additions and 22 deletions
Download patch file Download diff file Expand all files Collapse all files

5
openmc/mgxs/library.py
View file

@ -331,7 +331,7 @@ class Library(object):
def num_delayed_groups(self, num_delayed_groups):
cv.check_less_than('num delayed groups', num_delayed_groups,
MAX_DELAYED_GROUPS, equality=True)
openmc.mgxs.MAX_DELAYED_GROUPS, equality=True)
cv.check_greater_than('num delayed groups', num_delayed_groups, 0,
equality=True)
self._num_delayed_groups = num_delayed_groups
@ -422,7 +422,8 @@ class Library(object):
if self.num_delayed_groups == 0:
mgxs.delayed_groups = None
else:
delayed_groups = list(range(1,self.num_delayed_groups))
delayed_groups \
= list(range(1,self.num_delayed_groups+1))
mgxs.delayed_groups = delayed_groups
# If a tally trigger was specified, add it to the MGXS

5
tests/test_mgxs_library_condense/test_mgxs_library_condense.py
View file

@ -23,9 +23,6 @@ class MGXSTestHarness(PyAPITestHarness):
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize a six-delayed-group structure
delayed_groups = list(range(1,7))
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
@ -34,7 +31,7 @@ class MGXSTestHarness(PyAPITestHarness):
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES + \
openmc.mgxs.MDGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.delayed_groups = delayed_groups
self.mgxs_lib.num_delayed_groups = 6
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
self.mgxs_lib.build_library()

5
tests/test_mgxs_library_distribcell/test_mgxs_library_distribcell.py
View file

@ -22,9 +22,6 @@ class MGXSTestHarness(PyAPITestHarness):
# Initialize a one-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 20.])
# Initialize a six-delayed-group structure
delayed_groups = list(range(1,7))
# Initialize MGXS Library for a few cross section types
# for one material-filled cell in the geometry
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
@ -34,7 +31,7 @@ class MGXSTestHarness(PyAPITestHarness):
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES + \
openmc.mgxs.MDGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.delayed_groups = delayed_groups
self.mgxs_lib.num_delayed_groups = 6
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'distribcell'
cells = self.mgxs_lib.openmc_geometry.get_all_material_cells()

5
tests/test_mgxs_library_hdf5/test_mgxs_library_hdf5.py
View file

@ -24,9 +24,6 @@ class MGXSTestHarness(PyAPITestHarness):
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize a six-delayed-group structure
delayed_groups = list(range(1,7))
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
@ -35,7 +32,7 @@ class MGXSTestHarness(PyAPITestHarness):
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES + \
openmc.mgxs.MDGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.delayed_groups = delayed_groups
self.mgxs_lib.num_delayed_groups = 6
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
self.mgxs_lib.build_library()

5
tests/test_mgxs_library_mesh/test_mgxs_library_mesh.py
View file

@ -18,9 +18,6 @@ class MGXSTestHarness(PyAPITestHarness):
# Initialize a one-group structure
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 20.])
# Initialize a six-delayed-group structure
delayed_groups = list(range(1,7))
# Initialize MGXS Library for a few cross section types
# for one material-filled cell in the geometry
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
@ -30,7 +27,7 @@ class MGXSTestHarness(PyAPITestHarness):
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES + \
openmc.mgxs.MDGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.delayed_groups = delayed_groups
self.mgxs_lib.num_delayed_groups = 6
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'mesh'

5
tests/test_mgxs_library_no_nuclides/test_mgxs_library_no_nuclides.py
View file

@ -23,9 +23,6 @@ class MGXSTestHarness(PyAPITestHarness):
energy_groups = openmc.mgxs.EnergyGroups(group_edges=[0, 0.625e-6,
20.])
# Initialize a six-delayed-group structure
delayed_groups = list(range(1,7))
# Initialize MGXS Library for a few cross section types
self.mgxs_lib = openmc.mgxs.Library(self._input_set.geometry)
self.mgxs_lib.by_nuclide = False
@ -34,7 +31,7 @@ class MGXSTestHarness(PyAPITestHarness):
self.mgxs_lib.mgxs_types = openmc.mgxs.MGXS_TYPES + \
openmc.mgxs.MDGXS_TYPES
self.mgxs_lib.energy_groups = energy_groups
self.mgxs_lib.delayed_groups = delayed_groups
self.mgxs_lib.num_delayed_groups = 6
self.mgxs_lib.legendre_order = 3
self.mgxs_lib.domain_type = 'material'
self.mgxs_lib.build_library()