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46d8896132
Co-authored-by: Bor Kos <bor.kos@bakerhughes.com> Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
54 lines
1.8 KiB
Python
54 lines
1.8 KiB
Python
import numpy as np
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import openmc
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import pytest
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from openmc.utility_funcs import change_directory
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from tests.testing_harness import PyAPITestHarness
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@pytest.mark.parametrize("shared_secondary,particle", [
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(False, "photon"),
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(False, "neutron"),
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(True, "photon"),
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(True, "neutron")
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])
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def test_pulse_height(shared_secondary, particle):
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subdir = f"shared_{particle}" if shared_secondary else f"local_{particle}"
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with change_directory(subdir):
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openmc.reset_auto_ids()
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model = openmc.Model()
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# Define materials
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NaI = openmc.Material()
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NaI.set_density('g/cm3', 3.7)
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NaI.add_element('Na', 1.0)
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NaI.add_element('I', 1.0)
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# Define geometry: two spheres in each other
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s1 = openmc.Sphere(r=1)
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s2 = openmc.Sphere(r=2, boundary_type='vacuum')
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inner_sphere = openmc.Cell(name='inner sphere', fill=NaI, region=-s1)
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outer_sphere = openmc.Cell(name='outer sphere', region=+s1 & -s2)
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model.geometry = openmc.Geometry([inner_sphere, outer_sphere])
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# Define settings
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model.settings.run_mode = 'fixed source'
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model.settings.batches = 5
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model.settings.particles = 100
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model.settings.photon_transport = True
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model.settings.shared_secondary_bank = shared_secondary
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model.settings.source = openmc.IndependentSource(
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energy=openmc.stats.delta_function(1e6),
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particle=particle
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)
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# Define tallies
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tally = openmc.Tally(name="pht tally")
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tally.scores = ['pulse-height']
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cell_filter = openmc.CellFilter(inner_sphere)
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energy_filter = openmc.EnergyFilter(np.linspace(0, 1e6, 101))
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tally.filters = [cell_filter, energy_filter]
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model.tallies = [tally]
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harness = PyAPITestHarness('statepoint.5.h5', model)
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harness.main()
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