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45 lines
1.2 KiB
Python
45 lines
1.2 KiB
Python
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"""Test the Iterated Fission Probability (IFP) method to compute adjoint-weighted
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kinetics parameters using dedicated tallies."""
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import openmc
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import pytest
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from tests.testing_harness import PyAPITestHarness
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@pytest.fixture()
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def ifp_model():
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model = openmc.Model()
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# Material
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material = openmc.Material(name="core")
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material.add_nuclide("U235", 1.0)
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material.set_density('g/cm3', 16.0)
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# Geometry
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radius = 10.0
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sphere = openmc.Sphere(r=radius, boundary_type="vacuum")
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cell = openmc.Cell(region=-sphere, fill=material)
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model.geometry = openmc.Geometry([cell])
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# Settings
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model.settings.particles = 1000
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model.settings.batches = 20
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model.settings.inactive = 5
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model.settings.ifp_n_generation = 5
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space = openmc.stats.Box(*cell.bounding_box)
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model.settings.source = openmc.IndependentSource(
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space=space, constraints={'fissionable': True})
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# Tally IFP scores
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tally = openmc.Tally(name="ifp-scores")
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tally.scores = ["ifp-time-numerator", "ifp-beta-numerator", "ifp-denominator"]
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model.tallies = [tally]
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return model
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def test_iterated_fission_probability(ifp_model):
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harness = PyAPITestHarness("statepoint.20.h5", model=ifp_model)
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harness.main()
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