adding back files to be reviewed

tests/regression_tests/mg_basic_delayed/inputs_true.dat

@@ -0,0 +1,63 @@
+<?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="vec beta">
+    <density units="macro" value="1.0" />
+    <macroscopic name="mat_1" />
+  </material>
+  <material id="2" name="vec no beta">
+    <density units="macro" value="1.0" />
+    <macroscopic name="mat_2" />
+  </material>
+  <material id="3" name="matrix beta">
+    <density units="macro" value="1.0" />
+    <macroscopic name="mat_3" />
+  </material>
+  <material id="4" name="matrix no beta">
+    <density units="macro" value="1.0" />
+    <macroscopic name="mat_4" />
+  </material>
+  <material id="5" name="vec group beta">
+    <density units="macro" value="1.0" />
+    <macroscopic name="mat_5" />
+  </material>
+  <material id="6" name="matrix group beta">
+    <density units="macro" value="1.0" />
+    <macroscopic 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_delayed/results_true.dat

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+k-combined:
+1.003463E+00 2.173155E-02

tests/regression_tests/mg_basic_delayed/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])
+    n_dg = 2
+
+    mg_cross_sections_file = openmc.MGXSLibrary(groups)
+    mg_cross_sections_file.num_delayed_groups = n_dg
+
+    beta = np.array([0.003, 0.003])
+    one_m_beta = 1. - np.sum(beta)
+    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.]
+
+    # Make the base data that uses chi & nu-fission vectors with a beta
+    mat_1 = openmc.XSdata('mat_1', groups)
+    mat_1.order = 1
+    mat_1.num_delayed_groups = 2
+    mat_1.set_beta(beta)
+    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 that uses prompt and delayed version of nufiss and chi
+    mat_2 = openmc.XSdata('mat_2', groups)
+    mat_2.order = 1
+    mat_2.num_delayed_groups = 2
+    mat_2.set_prompt_nu_fission(one_m_beta * np.multiply(nu, fiss))
+    delay_nu_fiss = np.zeros((n_dg, groups.num_groups))
+    for dg in range(n_dg):
+        for g in range(groups.num_groups):
+            delay_nu_fiss[dg, g] = beta[dg] * nu[g] * fiss[g]
+    mat_2.set_delayed_nu_fission(delay_nu_fiss)
+    mat_2.set_absorption(absorption)
+    mat_2.set_scatter_matrix(scatter)
+    mat_2.set_total(total)
+    mat_2.set_chi_prompt(chi)
+    mat_2.set_chi_delayed(np.stack([chi] * n_dg))
+    mg_cross_sections_file.add_xsdata(mat_2)
+
+    # Make a version that uses a nu-fission matrix with a beta
+    mat_3 = openmc.XSdata('mat_3', groups)
+    mat_3.order = 1
+    mat_3.num_delayed_groups = 2
+    mat_3.set_beta(beta)
+    mat_3.set_nu_fission(np.outer(np.multiply(nu, fiss), chi))
+    mat_3.set_absorption(absorption)
+    mat_3.set_scatter_matrix(scatter)
+    mat_3.set_total(total)
+    mg_cross_sections_file.add_xsdata(mat_3)
+
+    # Make a version that uses prompt and delayed version of the nufiss matrix
+    mat_4 = openmc.XSdata('mat_4', groups)
+    mat_4.order = 1
+    mat_4.num_delayed_groups = 2
+    mat_4.set_prompt_nu_fission(one_m_beta *
+                                np.outer(np.multiply(nu, fiss), chi))
+    delay_nu_fiss = np.zeros((n_dg, groups.num_groups, groups.num_groups))
+    for dg in range(n_dg):
+        for g in range(groups.num_groups):
+            for go in range(groups.num_groups):
+                delay_nu_fiss[dg, g, go] = beta[dg] * nu[g] * fiss[g] * chi[go]
+    mat_4.set_delayed_nu_fission(delay_nu_fiss)
+    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 the base data that uses chi & nu-fiss vectors with a group-wise beta
+    mat_5 = openmc.XSdata('mat_5', groups)
+    mat_5.order = 1
+    mat_5.num_delayed_groups = 2
+    mat_5.set_beta(np.stack([beta] * groups.num_groups))
+    mat_5.set_nu_fission(np.multiply(nu, fiss))
+    mat_5.set_absorption(absorption)
+    mat_5.set_scatter_matrix(scatter)
+    mat_5.set_total(total)
+    mat_5.set_chi(chi)
+    mg_cross_sections_file.add_xsdata(mat_5)
+
+    # Make a version that uses a nu-fission matrix with a group-wise beta
+    mat_6 = openmc.XSdata('mat_6', groups)
+    mat_6.order = 1
+    mat_6.num_delayed_groups = 2
+    mat_6.set_beta(np.stack([beta] * groups.num_groups))
+    mat_6.set_nu_fission(np.outer(np.multiply(nu, fiss), chi))
+    mat_6.set_absorption(absorption)
+    mat_6.set_scatter_matrix(scatter)
+    mat_6.set_total(total)
+    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_delayed():
+    create_library()
+    model = slab_mg(num_regions=6, mat_names=['vec beta', 'vec no beta',
+                                              'matrix beta', 'matrix no beta',
+                                              'vec group beta',
+                                              'matrix group beta'])
+
+    harness = PyAPITestHarness('statepoint.10.h5', model)
+    harness.main()