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Setting fuel material by name in the dagmc test.

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This commit is contained in:
Patrick Shriwise 2019-03-16 08:08:23 -05:00
parent 5135353db5
commit 1f55d331b8
3 changed files with 4 additions and 4 deletions
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tests/regression_tests/dagmc/dagmc.h5m
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4
tests/regression_tests/dagmc/inputs_true.dat
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@ -1,10 +1,10 @@
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material depletable="true" id="40">
<material depletable="true" id="40" name="fuel">
<density units="g/cc" value="11" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="41">
<material id="41" name="water">
<density units="g/cc" value="1.0" />
<nuclide ao="2.0" name="H1" />
<nuclide ao="1.0" name="O16" />

4
tests/regression_tests/dagmc/test.py
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@ -30,12 +30,12 @@ def test_dagmc():
model.tallies = [tally]
# materials
u235 = openmc.Material()
u235 = openmc.Material(name="fuel")
u235.add_nuclide('U235', 1.0, 'ao')
u235.set_density('g/cc', 11)
u235.id = 40
water = openmc.Material()
water = openmc.Material(name="water")
water.add_nuclide('H1', 2.0, 'ao')
water.add_nuclide('O16', 1.0, 'ao')
water.set_density('g/cc', 1.0)