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97 lines
3.1 KiB
Python
97 lines
3.1 KiB
Python
import os
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import numpy as np
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import openmc
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from openmc.examples import slab_mg
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from tests.testing_harness import PyAPITestHarness
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def create_library():
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# Instantiate the energy group data and file object
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groups = openmc.mgxs.EnergyGroups(group_edges=[0.0, 0.625, 20.0e6])
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mg_cross_sections_file = openmc.MGXSLibrary(groups)
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# Make the base, isotropic data
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nu = [2.50, 2.50]
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fiss = np.array([0.002817, 0.097])
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capture = [0.008708, 0.02518]
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absorption = np.add(capture, fiss)
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scatter = np.array(
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[[[0.31980, 0.06694], [0.004555, -0.0003972]],
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[[0.00000, 0.00000], [0.424100, 0.05439000]]])
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total = [0.33588, 0.54628]
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chi = [1., 0.]
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mat_1 = openmc.XSdata('mat_1', groups)
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mat_1.order = 1
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mat_1.set_nu_fission(np.multiply(nu, fiss))
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mat_1.set_absorption(absorption)
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mat_1.set_scatter_matrix(scatter)
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mat_1.set_total(total)
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mat_1.set_chi(chi)
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mg_cross_sections_file.add_xsdata(mat_1)
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# Make a version of mat-1 which has a tabular representation of the
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# scattering vice Legendre with 33 points
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mat_2 = mat_1.convert_scatter_format('tabular', 33)
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mat_2.name = 'mat_2'
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mg_cross_sections_file.add_xsdata(mat_2)
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# Make a version of mat-1 which has a histogram representation of the
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# scattering vice Legendre with 33 bins
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mat_3 = mat_1.convert_scatter_format('histogram', 33)
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mat_3.name = 'mat_3'
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mg_cross_sections_file.add_xsdata(mat_3)
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# Make a version which uses a fission matrix vice chi & nu-fission
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mat_4 = openmc.XSdata('mat_4', groups)
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mat_4.order = 1
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mat_4.set_nu_fission(np.outer(np.multiply(nu, fiss), chi))
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mat_4.set_absorption(absorption)
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mat_4.set_scatter_matrix(scatter)
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mat_4.set_total(total)
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mg_cross_sections_file.add_xsdata(mat_4)
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# Make an angle-dependent version of mat_1 with 2 polar and 2 azim. angles
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mat_5 = mat_1.convert_representation('angle', 2, 2)
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mat_5.name = 'mat_5'
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mg_cross_sections_file.add_xsdata(mat_5)
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# Make a copy of mat_1 for testing microscopic cross sections
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mat_6 = openmc.XSdata('mat_6', groups)
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mat_6.order = 1
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mat_6.set_nu_fission(np.multiply(nu, fiss))
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mat_6.set_absorption(absorption)
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mat_6.set_scatter_matrix(scatter)
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mat_6.set_total(total)
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mat_6.set_chi(chi)
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mg_cross_sections_file.add_xsdata(mat_6)
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# Write the file
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mg_cross_sections_file.export_to_hdf5('2g.h5')
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class MGXSTestHarness(PyAPITestHarness):
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def _cleanup(self):
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super()._cleanup()
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f = '2g.h5'
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if os.path.exists(f):
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os.remove(f)
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def test_mg_basic():
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create_library()
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mat_names = ['base leg', 'base tab', 'base hist', 'base matrix',
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'base ang', 'micro']
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model = slab_mg(num_regions=6, mat_names=mat_names)
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# Modify the last material to be a microscopic combination of nuclides
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model.materials[-1] = openmc.Material(name='micro', material_id=6)
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model.materials[-1].set_density("sum")
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model.materials[-1].add_nuclide("mat_1", 0.5)
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model.materials[-1].add_nuclide("mat_6", 0.5)
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harness = PyAPITestHarness('statepoint.10.h5', model)
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harness.main()
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