Greetings,
I am getting some odd results for 3D meshes. Surprisingly, I just found this mailing list and I realize I should have come here before opening an issue but I’m posting a link anyway: https://github.com/openmc-dev/openmc/issues/1194
Content of issue:
Perhaps related to #1106 but I get some odd results if I specify a 3D mesh. In a sense, it appears to be “half” right:
sp = openmc.StatePoint(filename=str(*glob('statepoint*')))
tally = sp.get_tally()
goal = tally.get_slice(scores=[desired_score])
goal_array = goal.get_values().reshape(sp.meshes[1]._dimension)
Below is a plot of goal_array, shape [100, 100, 100], plotting every 10th axial slice:
Any ideas?
Some additional info:
materials.xml:
<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>/Users/sterlingbutters/odrive/AmazonDrive/PycharmProjects/OpenMC-Dash-InterFace/parameters/../nndc_hdf5/cross_sections.xml</cross_sections>
<material id="1" name="Fuel">
<density units="g/cm3" value="10.29769" />
<nuclide ao="4.4843e-06" name="U234" />
<nuclide ao="0.00055815" name="U235" />
<nuclide ao="0.022408" name="U238" />
<nuclide ao="0.045829" name="O16" />
</material>
<material id="2" name="Clad">
<density units="g/cm3" value="6.55" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="3" name="Water">
<density units="g/cm3" value="0.740582" />
<nuclide ao="0.049457" name="H1" />
<nuclide ao="0.024672" name="O16" />
<nuclide ao="8.0042e-06" name="B10" />
<nuclide ao="3.2218e-05" name="B11" />
</material>
</materials>
geometry.xml:
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="Fuel" region="-7" universe="1" />
<cell id="2" material="2" name="Clad" region="8 1 -2 3 -4 5 -6" universe="1" />
<cell id="3" material="3" name="Water" universe="1" />
<cell id="4" material="1" name="Fuel" region="-9" universe="3" />
<cell id="5" material="2" name="Clad" region="10 1 -2 3 -4 5 -6" universe="3" />
<cell id="6" material="3" name="Water" universe="3" />
<cell id="7" material="1" name="Fuel" region="-11" universe="4" />
<cell id="8" material="2" name="Clad" region="12 1 -2 3 -4 5 -6" universe="4" />
<cell id="9" material="3" name="Water" universe="4" />
<cell fill="2" id="10" name="Root Cell" region="1 -2 3 -4 5 -6" universe="5" />
<lattice id="2" name="TestAssembly">
<pitch>1.26 1.26</pitch>
<dimension>15 15</dimension>
<lower_left>-9.45 -9.45</lower_left>
<universes>
1 1 1 1 1 1 4 4 4 4 4 4 4 4 1
1 1 1 1 1 1 1 1 1 1 1 1 1 4 1
1 1 1 1 1 1 1 1 1 1 1 1 1 4 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 4 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 3 3 3 3 3 1 1 1 1 4 1
1 4 3 1 1 1 1 1 3 1 1 1 1 4 1
1 4 3 1 1 1 1 1 3 1 1 1 1 4 1
1 4 3 1 1 1 1 1 4 1 1 1 1 4 1
1 1 3 3 3 3 3 3 3 1 1 1 1 4 1
1 4 1 1 1 1 1 1 1 1 1 1 1 4 1
1 1 4 1 1 1 1 1 4 1 1 4 1 4 1
1 1 4 1 4 4 1 4 1 4 4 4 4 4 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
</lattice>
<surface boundary="reflective" coeffs="-9.45" id="1" type="x-plane" />
<surface boundary="reflective" coeffs="9.45" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="-9.45" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="9.45" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="-100.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="100.0" id="6" type="z-plane" />
<surface coeffs="0 0 0.4" id="7" name="Fuel Outer Radius" type="z-cylinder" />
<surface coeffs="0 0 0.45" id="8" name="Clad Outer Radius" type="z-cylinder" />
<surface coeffs="0 0 0.3" id="9" name="Fuel Outer Radius" type="z-cylinder" />
<surface coeffs="0 0 0.45" id="10" name="Clad Outer Radius" type="z-cylinder" />
<surface coeffs="0 0 0.43" id="11" name="Fuel Outer Radius" type="z-cylinder" />
<surface coeffs="0 0 0.45" id="12" name="Clad Outer Radius" type="z-cylinder" />
</geometry>
settings.xml:
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>100</batches>
<inactive>20</inactive>
<generations_per_batch>10</generations_per_batch>
<source strength="1.0">
<space type="box">
<parameters>-9.45 -9.45 -100.0 9.45 9.45 100.0</parameters>
</space>
</source>
<output>
<summary>true</summary>
<tallies>true</tallies>
</output>
<confidence_intervals>false</confidence_intervals>
<ptables>false</ptables>
<run_cmfd>false</run_cmfd>
<seed>1</seed>
<survival_biasing>false</survival_biasing>
<verbosity>7</verbosity>
</settings>
tallies.xml:
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" type="regular">
<dimension>100 100 100</dimension>
<lower_left>-9.45 -9.45 -100.0</lower_left>
<width>0.18899999999999997 0.18899999999999997 2.0</width>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1" name="Mesh">
<filters>1</filters>
<scores>flux absorption elastic fission total scatter</scores>
</tally>
</tallies>