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

Made source only fissionable for asymmetric lattice test

Browse source
This commit is contained in:
wbinventor@gmail.com 2016-02-03 11:18:50 -05:00
parent a62dc7868f
commit dd18376d3f
4 changed files with 10 additions and 8 deletions
Download patch file Download diff file Expand all files Collapse all files

2
openmc/tallies.py
View file

@ -2748,7 +2748,7 @@ class Tally(object):
bin_indices.append(bin_index)
num_bins += 1
find_filter.bins = set(find_filter.bins[bin_indices])
find_filter.bins = np.unique(find_filter.bins[bin_indices])
find_filter.num_bins = num_bins
# Update the new tally's filter strides

2
tests/test_asymmetric_lattice/inputs_true.dat
View file

@ -1 +1 @@
dd39c0ae6327e6e74cb077d56e37c112611b95c4c10d96203e672b3e7f928211cc991ec7ebbf9eeadabd968dcdcb651b250233169b62d43ef6994ab9a46cb34a
fe07eb28fd0dbb56edaecd510f5e8e4db7271e5c9aecf3d880cce92b69872a0aacf825b8e88cd2e9b1ff709f578b269b1835f53cf2561a390062e1e7e03b5276

2
tests/test_asymmetric_lattice/results_true.dat
View file

@ -1 +1 @@
7e75ad5b7979e65e52ce564bfbd8fac819013ef8ba35fe184569b452dd9a1ba98d267b6e33d357fdd1c943f201125ff8a4f8601147b87036525870528063dcae
cea61172ecad5554ef86f52d6adad6ad5e21931cf3d67feb37b8bf9d75e618786f638685e458051d4a39afe1a924fd651cf6674a88cf1f1842fd69cd851e1f17

12
tests/test_asymmetric_lattice/test_asymmetric_lattice.py
View file

@ -22,7 +22,6 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness):
# Extract all universes from the full core geometry
geometry = self._input_set.geometry.geometry
all_univs = geometry.get_all_universes()
print(all_univs.keys())
# Extract universes encapsulating fuel and water assemblies
water = all_univs[7]
@ -55,7 +54,7 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness):
# Over-ride geometry in the input set with this 3x3 lattice
self._input_set.geometry.geometry.root_universe = root_univ
# Initialize a "distribcell" filter for the cold fuel pin cell
# Initialize a "distribcell" filter for the fuel pin cell
distrib_filter = openmc.Filter(type='distribcell', bins=[27])
# Initialize the tallies
@ -70,11 +69,14 @@ class AsymmetricLatticeTestHarness(PyAPITestHarness):
# Assign the tallies file to the input set
self._input_set.tallies = tallies_file
# Specify summary output and correct source sampling box
self._input_set.build_default_settings()
# Specify summary output and correct source sampling box
source = Source(space=Box([-32, -32, 0], [32, 32, 32]))
source.only_fissionable = True
self._input_set.settings.source = source
self._input_set.settings.output = {'summary': True}
self._input_set.settings.source = Source(space=Box(
[0, 0, 0], [32.13, 32.13, 32.13]))
# Write input XML files
self._input_set.export()