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70 lines
2.6 KiB
Python
Executable file
70 lines
2.6 KiB
Python
Executable file
import openmc
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from tests.testing_harness import PyAPITestHarness
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class CreateFissionNeutronsTestHarness(PyAPITestHarness):
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def __init__(self, *args, **kwargs):
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super().__init__(*args, **kwargs)
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# Material is composed of H-1 and U-235
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mat = openmc.Material(material_id=1, name='mat')
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mat.set_density('atom/b-cm', 0.069335)
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mat.add_nuclide('H1', 40.0)
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mat.add_nuclide('U235', 1.0)
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self._model.materials = openmc.Materials([mat])
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# Cell is box with reflective boundary
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x1 = openmc.XPlane(surface_id=1, x0=-1)
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x2 = openmc.XPlane(surface_id=2, x0=1)
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y1 = openmc.YPlane(surface_id=3, y0=-1)
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y2 = openmc.YPlane(surface_id=4, y0=1)
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z1 = openmc.ZPlane(surface_id=5, z0=-1)
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z2 = openmc.ZPlane(surface_id=6, z0=1)
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for surface in [x1, x2, y1, y2, z1, z2]:
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surface.boundary_type = 'reflective'
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box = openmc.Cell(cell_id=1, name='box')
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box.region = +x1 & -x2 & +y1 & -y2 & +z1 & -z2
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box.fill = mat
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root = openmc.Universe(universe_id=0, name='root universe')
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root.add_cell(box)
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self._model.geometry = openmc.Geometry(root)
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# Set the running parameters
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settings_file = openmc.Settings()
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settings_file.run_mode = 'fixed source'
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settings_file.batches = 10
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settings_file.particles = 100
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settings_file.create_fission_neutrons = False
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bounds = [-1, -1, -1, 1, 1, 1]
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uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:])
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watt_dist = openmc.stats.Watt()
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settings_file.source = openmc.IndependentSource(space=uniform_dist,
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energy=watt_dist)
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self._model.settings = settings_file
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# Create tallies
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tallies = openmc.Tallies()
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tally = openmc.Tally(1)
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tally.scores = ['flux']
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tallies.append(tally)
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self._model.tallies = tallies
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def _get_results(self):
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"""Digest info in the statepoint and return as a string."""
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# Read the statepoint file.
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sp = openmc.StatePoint(self._sp_name)
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# Write out tally data.
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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_create_fission_neutrons():
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harness = CreateFissionNeutronsTestHarness('statepoint.10.h5',
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model=openmc.Model())
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harness.main()
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