Add a nuclide with Maxwell fission spectrum to energy_laws test

tests/regression_tests/energy_laws/geometry.xml

@@ -1,5 +0,0 @@
-<?xml version="1.0"?>
-<geometry>
-  <surface id="1" type="sphere" coeffs="0 0 0 100" boundary="vacuum"/>
-  <cell id="1" material="1" region="-1" />
-</geometry>

tests/regression_tests/energy_laws/inputs_true.dat

@@ -0,0 +1,23 @@
+<?xml version='1.0' encoding='utf-8'?>
+<geometry>
+  <cell id="1" material="1" region="-1" universe="1" />
+  <surface boundary="reflective" coeffs="0.0 0.0 0.0 100.0" id="1" type="sphere" />
+</geometry>
+<?xml version='1.0' encoding='utf-8'?>
+<materials>
+  <material depletable="true" id="1">
+    <density units="g/cm3" value="20.0" />
+    <nuclide ao="1.0" name="U233" />
+    <nuclide ao="1.0" name="Am244" />
+    <nuclide ao="1.0" name="H2" />
+    <nuclide ao="1.0" name="Na23" />
+    <nuclide ao="1.0" name="Ta181" />
+  </material>
+</materials>
+<?xml version='1.0' encoding='utf-8'?>
+<settings>
+  <run_mode>eigenvalue</run_mode>
+  <particles>1000</particles>
+  <batches>10</batches>
+  <inactive>5</inactive>
+</settings>

tests/regression_tests/energy_laws/materials.xml

@@ -1,10 +0,0 @@
-<?xml version="1.0"?>
-<materials>
-  <material id="1">
-    <density value="20" units="g/cc" />
-    <nuclide name="U233" ao="1.0" />
-    <nuclide name="H2" ao="1.0" />
-    <nuclide name="Na23" ao="1.0" />
-    <nuclide name="Ta181" ao="1.0" />
-  </material>
-</materials>

tests/regression_tests/energy_laws/results_true.dat

@@ -1,2 +1,2 @@
 k-combined:
-2.122164E+00 1.946222E-02
+2.466441E+00 1.500183E-02

tests/regression_tests/energy_laws/settings.xml

@@ -1,10 +0,0 @@
-<?xml version="1.0"?>
-<settings>
-  <run_mode>eigenvalue</run_mode>
-  <batches>10</batches>
-  <inactive>5</inactive>
-  <particles>1000</particles>
-  <source>
-    <space type="point" parameters="0. 0. 0." />
-  </source>
-</settings>

tests/regression_tests/energy_laws/test.py

@@ -2,23 +2,51 @@
 are not covered in other tests. It has a single material with the following
 nuclides:
 
-U-233: Only nuclide that has a Watt fission spectrum
+U233: Only nuclide that has a Watt fission spectrum
 
-H-2: Only nuclide that has an N-body phase space distribution, in this case for
+Am244: One of a few nuclides that has a Maxwell fission spectrum
+
+H2: Only nuclide that has an N-body phase space distribution, in this case for
 (n,2n)
 
-Na-23: Has an evaporation spectrum and also has reactions that have multiple
+Na23: Has an evaporation spectrum and also has reactions that have multiple
 angle-energy distributions, so it provides coverage for both of those
 situations.
 
-Ta-181: One of a few nuclides that has reactions with Kalbach-Mann distributions
+Ta181: One of a few nuclides that has reactions with Kalbach-Mann distributions
 that use linear-linear interpolation.
 
 """
 
-from tests.testing_harness import TestHarness
+import openmc
+import pytest
+
+from tests.testing_harness import PyAPITestHarness
 
 
-def test_energy_laws():
-    harness = TestHarness('statepoint.10.h5')
+@pytest.fixture
+def model():
+    model = openmc.model.Model()
+
+    m = openmc.Material()
+    m.set_density('g/cm3', 20.0)
+    m.add_nuclide('U233', 1.0)
+    m.add_nuclide('Am244', 1.0)
+    m.add_nuclide('H2', 1.0)
+    m.add_nuclide('Na23', 1.0)
+    m.add_nuclide('Ta181', 1.0)
+
+    s = openmc.Sphere(r=100.0, boundary_type='reflective')
+    c = openmc.Cell(fill=m, region=-s)
+    model.geometry = openmc.Geometry([c])
+
+    model.settings.batches = 10
+    model.settings.inactive = 5
+    model.settings.particles = 1000
+
+    return model
+
+
+def test_energy_laws(model):
+    harness = PyAPITestHarness('statepoint.10.h5', model)
     harness.main()