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changed test to PythonAPItestharness and added tests on surface filter behavior at boundaries
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guillaume
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68ad95ac95
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5ac313260c
2 changed files with 154 additions and 3 deletions
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@ -36,7 +36,6 @@ contains
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integer :: next_level ! next coordinate level to check
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integer :: surface_crossed ! surface which particle is on
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integer :: lattice_translation(3) ! in-lattice translation vector
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integer :: last_cell ! most recent cell particle was in
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integer :: n_event ! number of collisions/crossings
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real(8) :: d_boundary ! distance to nearest boundary
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real(8) :: d_collision ! sampled distance to collision
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@ -3,9 +3,161 @@
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import os
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import sys
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sys.path.insert(0, os.pardir)
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from testing_harness import TestHarness
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from testing_harness import PyAPITestHarness
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import openmc
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class CreateSurfaceTallyTestHarness(PyAPITestHarness):
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def _build_inputs(self):
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# Instantiate some Materials and register the appropriate Nuclides
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uo2 = openmc.Material(name='UO2 fuel at 2.4% wt enrichment')
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uo2.set_density('g/cm3', 10.29769)
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uo2.add_element('U', 1., enrichment=2.4)
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uo2.add_element('O', 2.)
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borated_water = openmc.Material(name='Borated water')
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borated_water.set_density('g/cm3', 0.740582)
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borated_water.add_element('B', 4.0e-5)
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borated_water.add_element('H', 5.0e-2)
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borated_water.add_element('O', 2.4e-2)
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borated_water.add_s_alpha_beta('c_H_in_H2O')
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# Instantiate a Materials collection and export to XML
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materials_file = openmc.Materials([uo2, borated_water])
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materials_file.export_to_xml()
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# Instantiate ZCylinder surfaces
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fuel_or = openmc.ZCylinder(surface_id=1, x0=0, y0=0, R=0.4, name='Fuel OR')
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left = openmc.XPlane(surface_id=2, x0=-0.62992, name='left')
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right = openmc.XPlane(x0=0.62992, name='right')
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bottom = openmc.YPlane(y0=-0.62992, name='bottom')
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top = openmc.YPlane(y0=0.62992, name='top')
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left.boundary_type = 'vacuum'
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right.boundary_type = 'reflective'
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top.boundary_type = 'reflective'
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bottom.boundary_type = 'reflective'
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# Instantiate Cells
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fuel = openmc.Cell(name='fuel')
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water = openmc.Cell(name='water')
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# Use surface half-spaces to define regions
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fuel.region = -fuel_or
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water.region = +fuel_or & -right & +bottom & -top
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# Register Materials with Cells
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fuel.fill = uo2
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water.fill = borated_water
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# Instantiate pin cell Universe
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pin_cell = openmc.Universe(name='pin cell')
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pin_cell.add_cells([fuel, water])
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# Instantiate root Cell and Universe
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root_cell = openmc.Cell(name='root cell')
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root_cell.region = +left & -right & +bottom & -top
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root_cell.fill = pin_cell
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root_univ = openmc.Universe(universe_id=0, name='root universe')
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root_univ.add_cell(root_cell)
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# Instantiate a Geometry, register the root Universe, and export to XML
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geometry = openmc.Geometry(root_univ)
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geometry.export_to_xml()
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# Instantiate a Settings object, set all runtime parameters, and export to XML
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settings_file = openmc.Settings()
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settings_file.batches = 10
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settings_file.inactive = 5
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settings_file.particles = 1000
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# Create an initial uniform spatial source distribution over fissionable zones
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bounds = [-0.62992, -0.62992, -1, 0.62992, 0.62992, 1]
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uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
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settings_file.source = openmc.source.Source(space=uniform_dist)
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settings_file.export_to_xml()
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# Tallies file
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tallies_file = openmc.Tallies()
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# Cell to cell tallies
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# These filters are same for all tallies
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energy_filter = openmc.EnergyFilter(two_groups)
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polar_filter = openmc.PolarFilter([0, np.pi / 4, np.pi])
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azimuthal_filter = openmc.AzimuthalFilter([0, np.pi / 4, np.pi])
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cell_to_cell_tallies = []
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tally_index = 0
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for cell1 in pin_cell.get_all_cells():
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for cell2 in pin_cell.get_all_cells():
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if cell1 != cell2 and abs(abs(cell1-cell2)-1) < 0.1: # no need for cell1 to cell1
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# Cell to cell filters for partial current
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cell_from_filter = openmc.CellFromFilter(cell1)
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cell_to_filter = openmc.CellFilter(cell2)
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cell_to_cell_tallies.append(openmc.Tally(tally_id=2*tally_index, name=str(cell1)+'-'+str(cell2)))
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cell_to_cell_tallies[2*tally_index].filters = [cell_from_filter, cell_to_filter, energy_filter, polar_filter, azimuthal_filter]
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cell_to_cell_tallies[2*tally_index].scores = ['current']
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cell_to_cell_tallies[2*tally_index].estimator = 'analog'
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tallies_file.append(cell_to_cell_tallies[2*tally_index])
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# Cell from + surface filters for partial current
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surface_filter = openmc.SurfaceFilter([1])
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cell_to_cell_tallies.append(openmc.Tally(tally_id=2*tally_index+1, name=str(cell1)+'-surface1'))
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cell_to_cell_tallies[2*tally_index+1].filters = [cell_from_filter, surface_filter, energy_filter, polar_filter, azimuthal_filter]
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cell_to_cell_tallies[2*tally_index+1].scores = ['current']
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cell_to_cell_tallies[2*tally_index+1].estimator = 'analog'
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tallies_file.append(cell_to_cell_tallies[2*tally_index+1])
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tally_index += 1
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# Surface filter on inner surface, for net current
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surface_filter = openmc.SurfaceFilter([1])
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cell_to_cell_tallies.append(openmc.Tally(tally_id=2*tally_index, name='surface1'))
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cell_to_cell_tallies[2*tally_index].filters = [surface_filter, energy_filter, polar_filter, azimuthal_filter]
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cell_to_cell_tallies[2*tally_index].scores = ['current']
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cell_to_cell_tallies[2*tally_index].estimator = 'analog'
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tallies_file.append(cell_to_cell_tallies[2*tally_index])
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# Surface filter on left surface, vacuum BC, for net current = leakage
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surface_filter = openmc.SurfaceFilter([1])
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cell_to_cell_tallies.append(openmc.Tally(tally_id=2*tally_index, name='surface1'))
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cell_to_cell_tallies[2*tally_index].filters = [surface_filter, energy_filter, polar_filter, azimuthal_filter]
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cell_to_cell_tallies[2*tally_index].scores = ['current']
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cell_to_cell_tallies[2*tally_index].estimator = 'analog'
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tallies_file.append(cell_to_cell_tallies[2*tally_index])
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# Surface filter on right surface, reflective, for net current = 0
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surface_filter = openmc.SurfaceFilter([1])
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cell_to_cell_tallies.append(openmc.Tally(tally_id=2*tally_index, name='surface1'))
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cell_to_cell_tallies[2*tally_index].filters = [surface_filter, energy_filter, polar_filter, azimuthal_filter]
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cell_to_cell_tallies[2*tally_index].scores = ['current']
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cell_to_cell_tallies[2*tally_index].estimator = 'analog'
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tallies_file.append(cell_to_cell_tallies[2*tally_index])
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tallies_file.export_to_xml()
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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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if __name__ == '__main__':
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harness = TestHarness('statepoint.10.h5')
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harness = CreateSurfaceTallyTestHarness('statepoint.10.h5')
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harness.main()
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