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57 lines
2.1 KiB
Python
57 lines
2.1 KiB
Python
import openmc
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import pytest
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from tests.testing_harness import config
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@pytest.fixture
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def model():
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# Create simple sphere model
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model = openmc.Model()
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mat = openmc.Material()
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mat.add_nuclide('U235', 1.0)
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mat.add_nuclide('H1', 1.0)
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mat.set_density('g/cm3', 5.0)
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sph = openmc.Sphere(r=10.0, boundary_type='vacuum')
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cell = openmc.Cell(fill=mat, region=-sph)
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model.geometry = openmc.Geometry([cell])
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model.settings.particles = 1000
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model.settings.inactive = 0
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model.settings.batches = 5
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model.settings.photon_transport = True
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# Add two tallies, one with heating by nuclide and one with total heating
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particle_filter = openmc.ParticleFilter(['neutron', 'photon'])
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heating_by_nuclide = openmc.Tally()
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heating_by_nuclide.filters = [particle_filter]
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heating_by_nuclide.nuclides = ['U235', 'H1']
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heating_by_nuclide.scores = ['heating']
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heating_total = openmc.Tally()
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heating_total.filters = [particle_filter]
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heating_total.scores = ['heating']
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model.tallies.extend([heating_by_nuclide, heating_total])
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return model
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def test_heating_by_nuclide(model, run_in_tmpdir):
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# If running in MPI mode, setup proper keyword arguments for run()
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kwargs = {'openmc_exec': config['exe']}
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if config['mpi']:
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kwargs['mpi_args'] = [config['mpiexec'], '-n', config['mpi_np']]
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sp_path = model.run(**kwargs)
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# Get tallies from resulting statepoint
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with openmc.StatePoint(sp_path) as sp:
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heating_by_nuclide = sp.tallies[model.tallies[0].id]
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heating_total = sp.tallies[model.tallies[1].id]
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for particle in heating_by_nuclide.filters[0].bins:
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# Get slice of each tally corresponding to a single particle
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kwargs = {'filters': [openmc.ParticleFilter], 'filter_bins': [(particle,)]}
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particle_slice_by_nuclide = heating_by_nuclide.get_values(**kwargs)
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particle_slice_total = heating_total.get_values(**kwargs)
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# Summing over nuclides should equal total
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assert particle_slice_by_nuclide.sum() == pytest.approx(particle_slice_total.sum())
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