Add fission photon production test

tests/regression_tests/photon_production_fission/inputs_true.dat

@@ -0,0 +1,49 @@
+<?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="10.0" />
+    <nuclide ao="1.0" name="U235" />
+  </material>
+</materials>
+<?xml version='1.0' encoding='utf-8'?>
+<settings>
+  <run_mode>eigenvalue</run_mode>
+  <particles>1000</particles>
+  <batches>5</batches>
+  <inactive>2</inactive>
+  <source strength="1.0">
+    <space type="point">
+      <parameters>0 0 0</parameters>
+    </space>
+  </source>
+  <photon_transport>true</photon_transport>
+</settings>
+<?xml version='1.0' encoding='utf-8'?>
+<tallies>
+  <filter id="1" type="particle">
+    <bins>neutron photon</bins>
+  </filter>
+  <tally id="1">
+    <filters>1</filters>
+    <nuclides>U235 total</nuclides>
+    <scores>fission heating heating-local</scores>
+    <estimator>tracklength</estimator>
+  </tally>
+  <tally id="2">
+    <filters>1</filters>
+    <nuclides>U235 total</nuclides>
+    <scores>fission heating heating-local</scores>
+    <estimator>collision</estimator>
+  </tally>
+  <tally id="3">
+    <filters>1</filters>
+    <nuclides>U235 total</nuclides>
+    <scores>fission heating heating-local</scores>
+    <estimator>analog</estimator>
+  </tally>
+</tallies>

tests/regression_tests/photon_production_fission/results_true.dat

@@ -0,0 +1,77 @@
+k-combined:
+2.223956E+00 2.598313E-03
+tally 1:
+2.600054E+00
+2.253433E+00
+4.390171E+08
+6.424554E+16
+0.000000E+00
+0.000000E+00
+2.600054E+00
+2.253433E+00
+4.390171E+08
+6.424554E+16
+0.000000E+00
+0.000000E+00
+0.000000E+00
+0.000000E+00
+2.491697E+07
+2.070245E+14
+0.000000E+00
+0.000000E+00
+0.000000E+00
+0.000000E+00
+2.491697E+07
+2.070245E+14
+0.000000E+00
+0.000000E+00
+tally 2:
+2.602512E+00
+2.258176E+00
+4.394176E+08
+6.437709E+16
+0.000000E+00
+0.000000E+00
+2.602512E+00
+2.258176E+00
+4.394176E+08
+6.437709E+16
+0.000000E+00
+0.000000E+00
+0.000000E+00
+0.000000E+00
+2.508579E+07
+2.098299E+14
+0.000000E+00
+0.000000E+00
+0.000000E+00
+0.000000E+00
+2.508579E+07
+2.098299E+14
+0.000000E+00
+0.000000E+00
+tally 3:
+2.663535E+00
+2.364845E+00
+4.394176E+08
+6.437709E+16
+0.000000E+00
+0.000000E+00
+2.663535E+00
+2.364845E+00
+4.394176E+08
+6.437709E+16
+0.000000E+00
+0.000000E+00
+0.000000E+00
+0.000000E+00
+2.495967E+07
+2.077339E+14
+0.000000E+00
+0.000000E+00
+0.000000E+00
+0.000000E+00
+2.504536E+07
+2.091625E+14
+0.000000E+00
+0.000000E+00

tests/regression_tests/photon_production_fission/test.py

@@ -0,0 +1,48 @@
+import openmc
+import pytest
+
+from tests.testing_harness import PyAPITestHarness
+
+
+@pytest.fixture
+def model():
+    model = openmc.model.Model()
+    mat = openmc.Material()
+    mat.set_density('g/cm3', 10.0)
+    mat.add_nuclide('U235', 1.0)
+    model.materials.append(mat)
+
+    sph = openmc.Sphere(r=100.0, boundary_type='reflective')
+    cell = openmc.Cell(fill=mat, region=-sph)
+    model.geometry = openmc.Geometry([cell])
+
+    model.settings.particles = 1000
+    model.settings.batches = 5
+    model.settings.inactive = 2
+    model.settings.photon_transport = True
+    model.settings.source = openmc.Source(space=openmc.stats.Point((0, 0, 0)))
+
+    particle_filter = openmc.ParticleFilter(['neutron', 'photon'])
+    tally_tracklength = openmc.Tally()
+    tally_tracklength.filters = [particle_filter]
+    tally_tracklength.scores = ['fission', 'heating', 'heating-local']
+    tally_tracklength.nuclides = ['U235', 'total']
+    tally_tracklength.estimator = 'tracklength'
+    tally_collision = openmc.Tally()
+    tally_collision.filters = [particle_filter]
+    tally_collision.scores = ['fission', 'heating', 'heating-local']
+    tally_collision.nuclides = ['U235', 'total']
+    tally_collision.estimator = 'collision'
+    tally_analog = openmc.Tally()
+    tally_analog.filters = [particle_filter]
+    tally_analog.scores = ['fission', 'heating', 'heating-local']
+    tally_analog.nuclides = ['U235', 'total']
+    tally_analog.estimator = 'analog'
+    model.tallies.extend([tally_tracklength, tally_collision, tally_analog])
+
+    return model
+
+
+def test_photon_production(model):
+    harness = PyAPITestHarness('statepoint.5.h5', model)
+    harness.main()