Add distributed material test

tests/test_distribmat/inputs_true.dat

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+dcb9a612432305763ad10aaaab3ed095716cbb73f6b357ec180d300ccf365f9781aac7b1f3228c8756ceccf6aa230d0e03cf18ef2c0bc21fba1f082c3d5d6896

tests/test_distribmat/results_true.dat

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+k-combined:
+1.433669E+00 7.069157E-03

tests/test_distribmat/test_distribmat.py

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+#!/usr/bin/env python
+
+import os
+import sys
+sys.path.insert(0, os.pardir)
+from testing_harness import TestHarness, PyAPITestHarness
+import openmc
+
+
+class DistribmatTestHarness(PyAPITestHarness):
+    def _build_inputs(self):
+        ####################
+        # Materials
+        ####################
+
+        moderator = openmc.Material(material_id=1)
+        moderator.set_density('g/cc', 1.0)
+        moderator.add_nuclide('H-1', 2.0)
+        moderator.add_nuclide('O-16', 1.0)
+
+        dense_fuel = openmc.Material(material_id=2)
+        dense_fuel.set_density('g/cc', 4.5)
+        dense_fuel.add_nuclide('U-235', 1.0)
+
+        light_fuel = openmc.Material(material_id=3)
+        light_fuel.set_density('g/cc', 2.0)
+        light_fuel.add_nuclide('U-235', 1.0)
+
+        mats_file = openmc.MaterialsFile()
+        mats_file.default_xs = '71c'
+        mats_file.add_materials([moderator, dense_fuel, light_fuel])
+        mats_file.export_to_xml()
+
+
+        ####################
+        # Geometry
+        ####################
+
+        c1 = openmc.Cell(cell_id=1)
+        c1.fill = moderator
+        mod_univ = openmc.Universe(universe_id=1)
+        mod_univ.add_cell(c1)
+
+        r0 = openmc.ZCylinder(R=0.3)
+        c11 = openmc.Cell(cell_id=11)
+        c11.region = -r0
+        c11.fill = [dense_fuel, light_fuel] + [dense_fuel]*2
+        c12 = openmc.Cell(cell_id=12)
+        c12.region = +r0
+        c12.fill = moderator
+        fuel_univ = openmc.Universe(universe_id=11)
+        fuel_univ.add_cells((c11, c12))
+
+        lat = openmc.RectLattice(lattice_id=101)
+        lat.dimension = [2, 2]
+        lat.lower_left = [-2.0, -2.0]
+        lat.pitch = [2.0, 2.0]
+        lat.universes = [[fuel_univ]*2]*2
+        lat.outer = mod_univ
+
+        x0 = openmc.XPlane(x0=-3.0)
+        x1 = openmc.XPlane(x0=3.0)
+        y0 = openmc.YPlane(y0=-3.0)
+        y1 = openmc.YPlane(y0=3.0)
+        for s in [x0, x1, y0, y1]:
+            s.boundary_type = 'reflective'
+        c101 = openmc.Cell(cell_id=101)
+        c101.region = +x0 & -x1 & +y0 & -y1
+        c101.fill = lat
+        root_univ = openmc.Universe(universe_id=0)
+        root_univ.add_cell(c101)
+
+        geometry = openmc.Geometry()
+        geometry.root_universe = root_univ
+        geo_file = openmc.GeometryFile()
+        geo_file.geometry = geometry
+        geo_file.export_to_xml()
+
+
+        ####################
+        # Settings
+        ####################
+
+        sets_file = openmc.SettingsFile()
+        sets_file.batches = 5
+        sets_file.inactive = 0
+        sets_file.particles = 1000
+        sets_file.set_source_space('box', [-1, -1, -1, 1, 1, 1])
+        #sets_file.output = {'summary': True}
+        sets_file.export_to_xml()
+
+
+#        ####################
+#        # Plots
+#        ####################
+#
+#        plots_file = openmc.PlotsFile()
+#
+#        plot = openmc.Plot(plot_id=1)
+#        plot.basis = 'xy'
+#        plot.color = 'cell'
+#        plot.filename = 'cellplot'
+#        plot.origin = (0, 0, 0)
+#        plot.width = (7, 7)
+#        plot.pixels = (400, 400)
+#        plots_file.add_plot(plot)
+#
+#        plot = openmc.Plot(plot_id=2)
+#        plot.basis = 'xy'
+#        plot.color = 'mat'
+#        plot.filename = 'matplot'
+#        plot.origin = (0, 0, 0)
+#        plot.width = (7, 7)
+#        plot.pixels = (400, 400)
+#        plots_file.add_plot(plot)
+#
+#        plots_file.export_to_xml()
+
+
+if __name__ == '__main__':
+    harness = DistribmatTestHarness('statepoint.5.*')
+    harness.main()