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More tests for material

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This commit is contained in:
Paul Romano 2018-01-24 14:29:31 -06:00
parent b81cbc29fb
commit 1432742fbf
1 changed files with 29 additions and 8 deletions
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37
tests/unit_tests/test_material.py
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@ -1,6 +1,7 @@
import openmc
import openmc.model
import openmc.stats
import openmc.examples
import pytest
@ -101,7 +102,7 @@ def test_repr():
repr(m)
def test_macroscopic():
def test_macroscopic(run_in_tmpdir):
m = openmc.Material(name='UO2')
m.add_macroscopic('UO2')
with pytest.raises(ValueError):
@ -116,17 +117,37 @@ def test_macroscopic():
with pytest.raises(ValueError):
m2.add_macroscopic('UO2')
# Make sure we can remove/add macroscopic
m.remove_macroscopic('UO2')
m.add_macroscopic('UO2')
repr(m)
# Make sure we can export a material with macroscopic data
mats = openmc.Materials([m])
mats.export_to_xml()
def test_paths():
model = openmc.examples.pwr_assembly()
model.geometry.determine_paths()
fuel = model.materials[0]
assert fuel.num_instances == 264
assert len(fuel.paths) == 264
def test_isotropic():
m = openmc.Material()
m.add_nuclide('U235', 1.0)
m.add_nuclide('O16', 2.0)
m.make_isotropic_in_lab()
assert m.isotropic == ['U235', 'O16']
m.isotropic = ['O16']
assert m.isotropic == ['O16']
m1 = openmc.Material()
m1.add_nuclide('U235', 1.0)
m1.add_nuclide('O16', 2.0)
m1.isotropic = ['O16']
assert m1.isotropic == ['O16']
m2 = openmc.Material()
m2.add_nuclide('H1', 1.0)
mats = openmc.Materials([m1, m2])
mats.make_isotropic_in_lab()
assert m1.isotropic == ['U235', 'O16']
assert m2.isotropic == ['H1']
def test_volume(run_in_tmpdir, sphere_model):