diff --git a/tests/regression_tests/dagmc/universes/inputs_true.dat b/tests/regression_tests/dagmc/universes/inputs_true.dat
new file mode 100644
index 0000000000..f8acb45ccc
--- /dev/null
+++ b/tests/regression_tests/dagmc/universes/inputs_true.dat
@@ -0,0 +1,47 @@
+
+
+ |
+
+
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+
+
+
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+
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+
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+ eigenvalue
+ 100
+ 10
+ 2
+
+
diff --git a/tests/regression_tests/dagmc/universes/results_true.dat b/tests/regression_tests/dagmc/universes/results_true.dat
new file mode 100644
index 0000000000..203d35efeb
--- /dev/null
+++ b/tests/regression_tests/dagmc/universes/results_true.dat
@@ -0,0 +1,2 @@
+k-combined:
+7.531408E-01 1.260163E-02
diff --git a/tests/regression_tests/dagmc/universes/test.py b/tests/regression_tests/dagmc/universes/test.py
index 0ed2025462..0144a0c3a8 100644
--- a/tests/regression_tests/dagmc/universes/test.py
+++ b/tests/regression_tests/dagmc/universes/test.py
@@ -1,4 +1,71 @@
import openmc
+import openmc.lib
+
+import pytest
+from tests.testing_harness import PyAPITestHarness
+
+pytestmark = pytest.mark.skipif(
+ not openmc.lib._dagmc_enabled(),
+ reason="DAGMC CAD geometry is not enabled.")
+
+
+class DAGMCUniverseTest(PyAPITestHarness):
+
+ def _build_inputs(self):
+ model = openmc.model.Model()
+
+ ### MATERIALS ###
+ fuel = openmc.Material(name='no-void fuel')
+ fuel.set_density('g/cc', 10.29769)
+ fuel.add_nuclide('U234', 0.93120485)
+ fuel.add_nuclide('U235', 0.00055815)
+ fuel.add_nuclide('U238', 0.022408)
+ fuel.add_nuclide('O16', 0.045829)
+
+ cladding = openmc.Material(name='clad')
+ cladding.set_density('g/cc', 6.55)
+ cladding.add_nuclide('Zr90', 0.021827)
+ cladding.add_nuclide('Zr91', 0.00476)
+ cladding.add_nuclide('Zr92', 0.0072758)
+ cladding.add_nuclide('Zr94', 0.0073734)
+ cladding.add_nuclide('Zr96', 0.0011879)
+
+ water = openmc.Material(name='water')
+ water.set_density('g/cc', 0.740582)
+ water.add_nuclide('H1', 0.049457)
+ water.add_nuclide('O16', 0.024672)
+ water.add_nuclide('B10', 8.0042e-06)
+ water.add_nuclide('B11', 3.2218e-05)
+ water.add_s_alpha_beta('c_H_in_H2O')
+
+ model.materials = openmc.Materials([fuel, cladding, water])
+
+ ### GEOMETRY ###
+ # create the DAGMC universe
+ pincell_univ = openmc.DAGMCUniverse(filename='dagmc.h5m', auto_ids=True)
+
+ left = openmc.XPlane(x0=-24.0, name='left', boundary_type='reflective')
+ right = openmc.XPlane(x0=24.0, name='right', boundary_type='reflective')
+ front = openmc.YPlane(y0=-24.0, name='front', boundary_type='reflective')
+ back = openmc.YPlane(y0=24.0, name='back', boundary_type='reflective')
+ bottom = openmc.ZPlane(z0=-20.0, name='bottom', boundary_type='vacuum')
+ top = openmc.ZPlane(z0=20.0, name='top', boundary_type='vacuum')
+
+ box = +left & -right & +front & -back & +bottom & -top
+
+ bounding_cell = openmc.Cell(fill=pincell_univ, region=box)
+
+ model.geometry = openmc.Geometry(root=[bounding_cell])
+
+ # settings
+ model.settings.particles = 100
+ model.settings.batches = 10
+ model.settings.inactive = 2
+ model.settings.output = {'summary' : False}
+
+ model.export_to_xml()
+
def test_dagmc_universes():
- openmc.run()
\ No newline at end of file
+ harness = DAGMCUniverseTest('statepoint.10.h5')
+ harness.main()
\ No newline at end of file