adding back files to be reviewed

tests/regression_tests/mg_basic/inputs_true.dat

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+<?xml version='1.0' encoding='utf-8'?>
+<geometry>
+  <cell id="1" material="1" region="1 -2" universe="0" />
+  <cell id="2" material="2" region="2 -3" universe="0" />
+  <cell id="3" material="3" region="3 -4" universe="0" />
+  <cell id="4" material="4" region="4 -5" universe="0" />
+  <cell id="5" material="5" region="5 -6" universe="0" />
+  <cell id="6" material="6" region="6 -7" universe="0" />
+  <surface boundary="reflective" coeffs="0.0" id="1" type="x-plane" />
+  <surface coeffs="154.90833333333333" id="2" type="x-plane" />
+  <surface coeffs="309.81666666666666" id="3" type="x-plane" />
+  <surface coeffs="464.725" id="4" type="x-plane" />
+  <surface coeffs="619.6333333333333" id="5" type="x-plane" />
+  <surface coeffs="774.5416666666666" id="6" type="x-plane" />
+  <surface boundary="vacuum" coeffs="929.45" id="7" type="x-plane" />
+</geometry>
+<?xml version='1.0' encoding='utf-8'?>
+<materials>
+  <cross_sections>2g.h5</cross_sections>
+  <material id="1" name="base leg">
+    <density units="macro" value="1.0" />
+    <macroscopic name="mat_1" />
+  </material>
+  <material id="2" name="base tab">
+    <density units="macro" value="1.0" />
+    <macroscopic name="mat_2" />
+  </material>
+  <material id="3" name="base hist">
+    <density units="macro" value="1.0" />
+    <macroscopic name="mat_3" />
+  </material>
+  <material id="4" name="base matrix">
+    <density units="macro" value="1.0" />
+    <macroscopic name="mat_4" />
+  </material>
+  <material id="5" name="base ang">
+    <density units="macro" value="1.0" />
+    <macroscopic name="mat_5" />
+  </material>
+  <material id="6" name="micro">
+    <density units="sum" />
+    <nuclide ao="0.5" name="mat_1" />
+    <nuclide ao="0.5" name="mat_6" />
+  </material>
+</materials>
+<?xml version='1.0' encoding='utf-8'?>
+<settings>
+  <run_mode>eigenvalue</run_mode>
+  <particles>1000</particles>
+  <batches>10</batches>
+  <inactive>5</inactive>
+  <source strength="1.0">
+    <space type="box">
+      <parameters>0.0 -1000.0 -1000.0 154.90833333333333 1000.0 1000.0</parameters>
+    </space>
+  </source>
+  <output>
+    <summary>false</summary>
+  </output>
+  <energy_mode>multi-group</energy_mode>
+  <tabular_legendre>
+    <enable>false</enable>
+  </tabular_legendre>
+</settings>

tests/regression_tests/mg_basic/results_true.dat

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+k-combined:
+1.005345E+00 1.109180E-02

tests/regression_tests/mg_basic/test.py

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