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d9b30bbbd5
Co-authored-by: Adam Nelson <1037107+nelsonag@users.noreply.github.com> Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
59 lines
1.9 KiB
Python
59 lines
1.9 KiB
Python
import openmc
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import numpy as np
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import pytest
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@pytest.fixture
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def one_group_lib():
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groups = openmc.mgxs.EnergyGroups([0.0, 20.0e6])
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xsdata = openmc.XSdata('slab_mat', groups)
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xsdata.order = 0
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xsdata.set_total([0.0])
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xsdata.set_absorption([0.0])
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xsdata.set_scatter_matrix([[[0.0]]])
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mg_library = openmc.MGXSLibrary(groups)
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mg_library.add_xsdata(xsdata)
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name = 'mgxs.h5'
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mg_library.export_to_hdf5(name)
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yield name
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@pytest.fixture
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def slab_model(one_group_lib):
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model = openmc.Model()
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mat = openmc.Material(name='slab_material')
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mat.set_density('macro', 1.0)
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mat.add_macroscopic('slab_mat')
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model.materials = openmc.Materials([mat])
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model.materials.cross_sections = one_group_lib
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x_min = openmc.XPlane(x0=0.0, boundary_type='vacuum')
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x_max = openmc.XPlane(x0=10.0, boundary_type='vacuum')
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y_min = openmc.YPlane(y0=-10.0, boundary_type='vacuum')
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y_max = openmc.YPlane(y0=10.0, boundary_type='vacuum')
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z_min = openmc.ZPlane(z0=-10.0, boundary_type='vacuum')
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z_max = openmc.ZPlane(z0=19.0, boundary_type='vacuum')
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cell = openmc.Cell(fill=mat, region=+z_min & -x_max & +y_min & -y_max & +z_min & -z_max)
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model.geometry = openmc.Geometry([cell])
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model.settings = openmc.Settings()
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model.settings.energy_mode = 'multi-group'
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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 = 10
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source = openmc.IndependentSource()
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source.space = openmc.stats.Point((5.0, 0.0, 0.0))
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model.settings.source = source
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return model
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def test_inverse_velocity(run_in_tmpdir, slab_model):
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tally = openmc.Tally()
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tally.scores = ['flux','inverse-velocity']
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slab_model.tallies = [tally]
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slab_model.run(apply_tally_results=True)
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inverse_velocity = tally.mean.squeeze()[1]/tally.mean.squeeze()[0]
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assert inverse_velocity == pytest.approx(1.6144e-5, rel=1e-4)
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