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59 lines
1.9 KiB
Python
59 lines
1.9 KiB
Python
import numpy as np
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import openmc
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import openmc.stats
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from tests.testing_harness import PyAPITestHarness
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class FixedSourceTestHarness(PyAPITestHarness):
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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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outstr = ''
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with openmc.StatePoint(self._sp_name) as sp:
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# Write out tally data.
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for i, tally_ind in enumerate(sp.tallies):
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tally = sp.tallies[tally_ind]
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results = np.zeros((tally.sum.size*2, ))
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results[0::2] = tally.sum.ravel()
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results[1::2] = tally.sum_sq.ravel()
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results = ['{0:12.6E}'.format(x) for x in results]
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outstr += 'tally ' + str(i + 1) + ':\n'
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outstr += '\n'.join(results) + '\n'
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gt = sp.global_tallies
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outstr += 'leakage:\n'
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outstr += '{0:12.6E}'.format(gt[gt['name'] == b'leakage'][0]['sum']) + '\n'
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outstr += '{0:12.6E}'.format(gt[gt['name'] == b'leakage'][0]['sum_sq']) + '\n'
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return outstr
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def test_fixed_source():
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mat = openmc.Material()
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mat.add_nuclide('O16', 1.0)
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mat.add_nuclide('U238', 0.0001)
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mat.set_density('g/cc', 7.5)
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surf = openmc.Sphere(r=10.0, boundary_type='vacuum')
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cell = openmc.Cell(fill=mat, region=-surf)
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model = openmc.model.Model()
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model.geometry.root_universe = openmc.Universe(cells=[cell])
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model.materials.append(mat)
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model.settings.run_mode = 'fixed source'
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model.settings.batches = 10
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model.settings.particles = 100
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model.settings.temperature = {'default': 294}
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model.settings.source = openmc.IndependentSource(space=openmc.stats.Point(),
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strength=10.0)
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tally = openmc.Tally()
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tally.scores = ['flux']
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model.tallies.append(tally)
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harness = FixedSourceTestHarness('statepoint.10.h5', model)
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harness.main()
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