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63 lines
2 KiB
Python
63 lines
2 KiB
Python
from random import uniform
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import pytest
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import openmc
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def inf_medium_model(cutoff_energy, source_energy):
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"""Infinite medium problem with a monoenergetic photon source"""
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model = openmc.Model()
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m = openmc.Material()
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m.add_nuclide('Zr90', 1.0)
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m.set_density('g/cm3', 1.0)
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sph = openmc.Sphere(r=100.0, boundary_type='reflective')
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cell = openmc.Cell(fill=m, region=-sph)
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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.source = openmc.IndependentSource(
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particle='photon',
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energy=openmc.stats.Discrete([source_energy], [1.0]),
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)
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model.settings.particles = 100
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model.settings.batches = 10
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model.settings.cutoff = {'energy_photon': cutoff_energy}
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tally_flux = openmc.Tally(name='flux')
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tally_flux.filters = [
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openmc.EnergyFilter([0.0, cutoff_energy, source_energy]),
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openmc.ParticleFilter(['photon'])
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]
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tally_flux.scores = ['flux']
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tally_heating = openmc.Tally(name='heating')
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tally_heating.scores = ['heating']
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model.tallies = openmc.Tallies([tally_flux, tally_heating])
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return model
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def test_energy_cutoff(run_in_tmpdir):
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# Pick a random cutoff energy between 1 and 5 keV
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cutoff_energy = uniform(1e3, 5e3)
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# Pick a random source energy some factor higher than cutoff energy
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source_energy = uniform(10, 20) * cutoff_energy
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# Create model and run simulation
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model = inf_medium_model(cutoff_energy, source_energy)
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statepoint_path = model.run()
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# Get resulting flux and heating values
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with openmc.StatePoint(statepoint_path) as sp:
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flux = sp.get_tally(name='flux').mean.ravel()
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heating = sp.get_tally(name='heating').mean.ravel()
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# There should be no flux below the cutoff energy (first bin in the tally)
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assert flux[0] == 0.0
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assert flux[1] > 0.0
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# Despite killing particles below the cutoff, the total heating should be
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# equal to the source energy
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assert heating[0] == pytest.approx(source_energy)
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