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Removing unecessary nuclides

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This commit is contained in:
Patrick Shriwise 2023-04-13 22:05:38 -05:00
parent 304443070b
commit 3a22be87a9
1 changed files with 6 additions and 17 deletions
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23
tests/unit_tests/dagmc/test_lost_particles.py
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@ -19,28 +19,17 @@ def broken_dagmc_model(request):
### MATERIALS ###
fuel = openmc.Material(name='no-void fuel')
fuel.set_density('g/cc', 10.29769)
fuel.add_nuclide('U234', 0.93120485)
fuel.add_nuclide('U235', 0.00055815)
fuel.add_nuclide('U238', 0.022408)
fuel.add_nuclide('O16', 0.045829)
fuel.add_nuclide('U233', 1.0)
cladding = openmc.Material(name='clad')
cladding.set_density('g/cc', 6.55)
cladding.add_nuclide('Zr90', 0.021827)
cladding.add_nuclide('Zr91', 0.00476)
cladding.add_nuclide('Zr92', 0.0072758)
cladding.add_nuclide('Zr94', 0.0073734)
cladding.add_nuclide('Zr96', 0.0011879)
cladding.add_nuclide('Zr90', 1.0)
water = openmc.Material(name='water')
water.set_density('g/cc', 0.740582)
water.add_nuclide('H1', 0.049457)
water.add_nuclide('O16', 0.024672)
water.add_nuclide('B10', 8.0042e-06)
water.add_nuclide('B11', 3.2218e-05)
water.add_s_alpha_beta('c_H_in_H2O')
h1 = openmc.Material(name='water')
h1.set_density('g/cc', 0.75)
h1.add_nuclide('H1', 1.0)
model.materials = openmc.Materials([fuel, cladding, water])
model.materials = openmc.Materials([fuel, cladding, h1])
### GEOMETRY ###
# create the DAGMC universe using a model that has many triangles