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Add photon tests
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10 changed files with 248 additions and 5 deletions
41
tests/regression_tests/photon_source/inputs_true.dat
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41
tests/regression_tests/photon_source/inputs_true.dat
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<?xml version='1.0' encoding='utf-8'?>
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<geometry>
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<cell id="13" material="13" region="-9" universe="9" />
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<surface boundary="reflective" coeffs="0.0 0.0 0.0 1000000000.0" id="9" type="sphere" />
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</geometry>
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<?xml version='1.0' encoding='utf-8'?>
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<materials>
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<material id="13">
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<density units="g/cm3" value="0.998207" />
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<nuclide ao="0.11187657362844" name="H1" />
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<nuclide ao="1.7426371559999997e-05" name="H2" />
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<nuclide ao="0.8877694078259999" name="O16" />
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<nuclide ao="0.000336592174" name="O17" />
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</material>
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</materials>
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<?xml version='1.0' encoding='utf-8'?>
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<settings>
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<run_mode>fixed source</run_mode>
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<particles>10000</particles>
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<batches>1</batches>
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<source particle="photon" strength="1.0">
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<space type="point">
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<parameters>0 0 0</parameters>
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</space>
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<angle type="isotropic" />
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<energy type="discrete">
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<parameters>10000000.0 1.0</parameters>
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</energy>
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</source>
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<electron_treatment>ttb</electron_treatment>
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<photon_transport>true</photon_transport>
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<cutoff>
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<energy_photon>1000.0</energy_photon>
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</cutoff>
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</settings>
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<?xml version='1.0' encoding='utf-8'?>
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<tallies>
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<tally id="1">
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<scores>flux</scores>
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</tally>
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</tallies>
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3
tests/regression_tests/photon_source/results_true.dat
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3
tests/regression_tests/photon_source/results_true.dat
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tally 1:
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sum = 2.254985E+02
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sum_sq = 5.084955E+04
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61
tests/regression_tests/photon_source/test.py
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tests/regression_tests/photon_source/test.py
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from math import pi
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import numpy as np
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import openmc
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from tests.testing_harness import PyAPITestHarness
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class SourceTestHarness(PyAPITestHarness):
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def _build_inputs(self):
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mat = openmc.Material()
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mat.set_density('g/cm3', 0.998207)
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mat.add_element('H', 0.111894)
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mat.add_element('O', 0.888106)
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materials = openmc.Materials([mat])
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materials.export_to_xml()
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sphere = openmc.Sphere(R=1.0e9, boundary_type='reflective')
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inside_sphere = openmc.Cell()
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inside_sphere.region = -sphere
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inside_sphere.fill = mat
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root = openmc.Universe()
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root.add_cell(inside_sphere)
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geometry = openmc.Geometry(root)
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geometry.export_to_xml()
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source = openmc.Source()
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source.space = openmc.stats.Point((0, 0, 0))
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source.angle = openmc.stats.Isotropic()
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source.energy = openmc.stats.Discrete([10.0e6], [1.0])
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source.particle = 'photon'
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settings = openmc.Settings()
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settings.particles = 10000
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settings.batches = 1
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settings.photon_transport = True
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settings.electron_treatment = 'ttb'
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settings.cutoff = {'energy_photon' : 1000.0}
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settings.run_mode = 'fixed source'
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settings.source = source
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settings.export_to_xml()
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tally = openmc.Tally()
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tally.scores = ['flux']
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tallies = openmc.Tallies([tally])
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tallies.export_to_xml()
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def _get_results(self):
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sp = openmc.StatePoint(self._sp_name)
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outstr = ''
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t = sp.get_tally()
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outstr += 'tally {}:\n'.format(t.id)
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outstr += 'sum = {:12.6E}\n'.format(t.sum[0, 0, 0])
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outstr += 'sum_sq = {:12.6E}\n'.format(t.sum_sq[0, 0, 0])
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return outstr
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def test_source():
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harness = SourceTestHarness('statepoint.1.h5')
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harness.main()
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