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1702b4554b
Co-authored-by: church89 <l.chierici89@gmail.com> Co-authored-by: Paul Romano <paul.k.romano@gmail.com>
95 lines
3.5 KiB
Python
95 lines
3.5 KiB
Python
import os
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import glob
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import hashlib
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import openmc
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from tests.testing_harness import PyAPITestHarness
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class AsymmetricLatticeTestHarness(PyAPITestHarness):
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def __init__(self, *args, **kwargs):
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super().__init__(*args, **kwargs)
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# Extract universes encapsulating fuel and water assemblies
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geometry = self._model.geometry
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water = geometry.get_universes_by_name('water assembly (hot)')[0]
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fuel = geometry.get_universes_by_name('fuel assembly (hot)')[0]
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# Construct a 3x3 lattice of fuel assemblies
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core_lat = openmc.RectLattice(name='3x3 Core Lattice', lattice_id=202)
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core_lat.lower_left = (-32.13, -32.13)
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core_lat.pitch = (21.42, 21.42)
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core_lat.universes = [[fuel, water, water],
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[fuel, fuel, fuel],
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[water, water, water]]
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# Create bounding surfaces
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min_x = openmc.XPlane(-32.13, boundary_type='reflective')
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max_x = openmc.XPlane(+32.13, boundary_type='reflective')
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min_y = openmc.YPlane(-32.13, boundary_type='reflective')
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max_y = openmc.YPlane(+32.13, boundary_type='reflective')
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min_z = openmc.ZPlane(0, boundary_type='reflective')
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max_z = openmc.ZPlane(+32.13, boundary_type='reflective')
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# Define root universe
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root_univ = openmc.Universe(universe_id=0, name='root universe')
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root_cell = openmc.Cell(cell_id=1)
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root_cell.region = +min_x & -max_x & +min_y & -max_y & +min_z & -max_z
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root_cell.fill = core_lat
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root_univ.add_cell(root_cell)
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# Over-ride geometry in the input set with this 3x3 lattice
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self._model.geometry.root_universe = root_univ
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# Initialize a "distribcell" filter for the fuel pin cell
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distrib_filter = openmc.DistribcellFilter(27)
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# Initialize the tallies
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tally = openmc.Tally(name='distribcell tally', tally_id=27)
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tally.filters.append(distrib_filter)
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tally.scores.append('nu-fission')
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# Assign the tallies file to the input set
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self._model.tallies.append(tally)
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# Specify summary output and correct source sampling box
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self._model.settings.source = openmc.IndependentSource(
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space=openmc.stats.Box([-32, -32, 0], [32, 32, 32]),
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constraints={'fissionable': True}
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)
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def _get_results(self, hash_output=True):
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"""Digest info in statepoint and summary and return as a string."""
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# Read the statepoint file
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statepoint = glob.glob(os.path.join(os.getcwd(), self._sp_name))[0]
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sp = openmc.StatePoint(statepoint)
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# Extract the tally of interest
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tally = sp.get_tally(name='distribcell tally')
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# Create a string of all mean, std. dev. values for both tallies
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outstr = ''
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outstr += '\n'.join(map('{:.8e}'.format, tally.mean.flatten())) + '\n'
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outstr += '\n'.join(map('{:.8e}'.format, tally.std_dev.flatten())) + '\n'
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# Extract fuel assembly lattices from the summary
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cells = sp.summary.geometry.get_all_cells()
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fuel_cell = cells[27]
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# Append a string of lattice distribcell offsets to the string
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outstr += '\n'.join(fuel_cell.paths) + '\n'
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# Hash the results if necessary
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if hash_output:
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sha512 = hashlib.sha512()
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sha512.update(outstr.encode('utf-8'))
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outstr = sha512.hexdigest()
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return outstr
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def test_asymmetric_lattice():
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harness = AsymmetricLatticeTestHarness('statepoint.10.h5')
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harness.main()
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