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43 lines
1.1 KiB
Python
43 lines
1.1 KiB
Python
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import numpy as np
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import openmc
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import pytest
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@pytest.fixture
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def empty_sphere():
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openmc.reset_auto_ids()
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model = openmc.Model()
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surf = openmc.Sphere(r=10, boundary_type='vacuum')
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cell = openmc.Cell(region=-surf)
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model.geometry = openmc.Geometry([cell])
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model.settings.run_mode = 'fixed source'
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model.settings.batches = 3
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model.settings.particles = 1000
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tally = openmc.Tally()
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tally.scores = ['total', 'elastic']
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tally.nuclides = ['U235']
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tally.multiply_density = False
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model.tallies.append(tally)
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return model
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def test_equivalent_microxs(empty_sphere, run_in_tmpdir):
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sp_file = empty_sphere.run()
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with openmc.StatePoint(sp_file) as sp:
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tally1 = sp.tallies[1]
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mat = openmc.Material()
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mat.add_nuclide('H1', 1e-16)
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empty_sphere.geometry.get_all_cells()[1].fill = mat
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sp_file = empty_sphere.run()
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with openmc.StatePoint(sp_file) as sp:
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tally2 = sp.tallies[1]
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assert np.isclose(tally1.mean.sum(), tally2.mean.sum(), rtol=1e-10, atol=0)
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assert tally1.mean.sum() > 0
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