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Addressing comments from @paulromano.
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parent
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commit
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3 changed files with 44 additions and 45 deletions
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@ -1,39 +1,20 @@
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<?xml version='1.0' encoding='utf-8'?>
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<geometry>
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<cell id="1" material="1" name="Fuel" region="-1" universe="0" />
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<cell id="2" material="2" name="Cladding" region="1 -2" universe="0" />
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<cell id="3" material="3" name="Water" region="2 3 -4 5 -6" universe="0" />
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<surface coeffs="0 0 0.39218" id="1" name="Fuel OR" type="z-cylinder" />
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<surface coeffs="0 0 0.4572" id="2" name="Clad OR" type="z-cylinder" />
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<surface boundary="reflective" coeffs="-0.63" id="3" name="left" type="x-plane" />
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<surface boundary="reflective" coeffs="0.63" id="4" name="right" type="x-plane" />
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<surface boundary="reflective" coeffs="-0.63" id="5" name="bottom" type="y-plane" />
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<surface boundary="reflective" coeffs="0.63" id="6" name="top" type="y-plane" />
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<cell id="1" material="1" region="-1" universe="1" />
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<cell id="2" material="2" region="1 -2" universe="1" />
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<surface coeffs="0.0 0.0 1.5" id="1" type="z-cylinder" />
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<surface boundary="reflective" coeffs="0.0 0.0 3.0" id="2" type="z-cylinder" />
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</geometry>
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<?xml version='1.0' encoding='utf-8'?>
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<materials>
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<material depletable="true" id="1" name="UO2 (2.4%)">
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<density units="g/cm3" value="10.29769" />
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<nuclide ao="4.4843e-06" name="U234" />
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<nuclide ao="0.00055815" name="U235" />
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<nuclide ao="0.022408" name="U238" />
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<nuclide ao="0.045829" name="O16" />
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<material depletable="true" id="1" name="fuel">
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<density units="g/cc" value="11" />
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<nuclide ao="1.0" name="U235" />
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</material>
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<material id="2" name="Zircaloy">
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<density units="g/cm3" value="6.55" />
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<nuclide ao="0.021827" name="Zr90" />
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<nuclide ao="0.00476" name="Zr91" />
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<nuclide ao="0.0072758" name="Zr92" />
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<nuclide ao="0.0073734" name="Zr94" />
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<nuclide ao="0.0011879" name="Zr96" />
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</material>
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<material id="3" name="Hot borated water">
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<density units="g/cm3" value="0.740582" />
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<nuclide ao="0.049457" name="H1" />
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<nuclide ao="0.024672" name="O16" />
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<nuclide ao="8.0042e-06" name="B10" />
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<nuclide ao="3.2218e-05" name="B11" />
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<sab name="c_H_in_H2O" />
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<material id="2" name="water">
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<density units="g/cc" value="1.0" />
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<nuclide ao="2.0" name="H1" />
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<nuclide ao="1.0" name="O16" />
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</material>
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</materials>
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<?xml version='1.0' encoding='utf-8'?>
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@ -42,9 +23,4 @@
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<particles>100</particles>
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<batches>10</batches>
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<inactive>1</inactive>
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<source strength="1.0">
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<space type="fission">
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<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
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</space>
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</source>
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</settings>
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@ -1,9 +1,7 @@
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k-combined:
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1.108161E+00 3.345885E-02
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1.857752E+00 2.922425E-02
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tally 1:
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1.178481E+02
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1.548363E+03
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4.198718E+01
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1.962188E+02
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2.252008E+02
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5.647830E+03
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5.337194E+01
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3.209877E+02
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1.621671E+02
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2.939588E+03
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@ -35,15 +35,16 @@ def cpp_driver(request):
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os.environ['CXX'] = 'mpicxx'
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try:
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print("Building driver")
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# Run cmake/make to build the shared libary
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subprocess.run(['cmake', os.path.pardir], check=True)
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subprocess.run(['make'], check=True)
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os.chdir(os.path.pardir)
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yield "./build/cpp_driver"
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finally:
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# Remove local build directory when test is complete
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os.chdir(os.path.pardir)
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shutil.rmtree('build')
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@ -65,10 +66,34 @@ class ExternalDriverTestHarness(PyAPITestHarness):
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def test_cpp_driver(cpp_driver):
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model = openmc.examples.pwr_pin_cell()
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model = openmc.model.Model()
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# materials
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u235 = openmc.Material(name="fuel")
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u235.add_nuclide('U235', 1.0, 'ao')
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u235.set_density('g/cc', 11)
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water = openmc.Material(name="water")
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water.add_nuclide('H1', 2.0, 'ao')
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water.add_nuclide('O16', 1.0, 'ao')
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water.set_density('g/cc', 1.0)
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mats = openmc.Materials([u235, water])
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model.materials = mats
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# geometry
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fuel_or = openmc.ZCylinder(r=1.5)
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coolant_or = openmc.ZCylinder(r=3.0, boundary_type='reflective')
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fuel = openmc.Cell(fill=u235, region=-fuel_or)
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coolant = openmc.Cell(fill=water, region=+fuel_or & -coolant_or)
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model.geometry = openmc.Geometry([fuel, coolant])
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model.settings.particles = 100
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model.settings.batches = 10
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model.settings.inactive = 1
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harness = ExternalDriverTestHarness(cpp_driver, 'statepoint.10.h5', model)
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harness._build_inputs()
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harness.main()
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