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Updating lattice_hex_coincident test to use Python API.
This commit is contained in:
Patrick Shriwise
parent
7351773b29
commit
33c1f64100
5 changed files with 227 additions and 83 deletions
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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" region="-1 2 -3" universe="1" />
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<cell id="2" material="2" region="1" universe="1" />
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<cell id="3" material="6" region="-4 2 -3" universe="2" />
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<cell id="4" material="7" region="4 -5 2 -3" universe="2" />
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<cell id="5" material="4" region="5 -6 2 -3" universe="2" />
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<cell id="6" material="2" region="6 2 -3" universe="2" />
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<cell id="7" material="2" universe="3" />
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<cell fill="4" id="8" name="container cell" region="-7 8 -9 10 11 -12 2 -3" universe="5" />
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<hex_lattice id="4" n_rings="2">
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<pitch>1.4</pitch>
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<outer>3</outer>
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<center>0.0 0.0</center>
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<universes>
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2
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2 2
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1
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2 2
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2</universes>
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</hex_lattice>
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<surface coeffs="0.0 0.0 0.7" id="1" type="z-cylinder" />
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<surface boundary="reflective" coeffs="0.0" id="2" type="z-plane" />
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<surface boundary="reflective" coeffs="10.0" id="3" type="z-plane" />
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<surface coeffs="0.0 0.0 0.293" id="4" type="z-cylinder" />
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<surface coeffs="0.0 0.0 0.35" id="5" type="z-cylinder" />
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<surface coeffs="0.0 0.0 0.352" id="6" type="z-cylinder" />
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<surface boundary="reflective" coeffs="1.4" id="7" type="y-plane" />
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<surface boundary="reflective" coeffs="-1.4" id="8" type="y-plane" />
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<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 2.8" id="9" type="plane" />
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<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 -2.8" id="10" type="plane" />
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<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 -2.8" id="11" type="plane" />
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<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 2.8" id="12" type="plane" />
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</geometry>
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@ -0,0 +1,81 @@
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<?xml version='1.0' encoding='utf-8'?>
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<geometry>
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<cell id="13" material="13" region="-9 10 -11" universe="9" />
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<cell id="14" material="14" region="9" universe="9" />
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<cell id="15" material="16" name="coolant" region="-12 10 -11" universe="10" />
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<cell id="16" material="17" name="zirconium_shell" region="12 -13 10 -11" universe="10" />
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<cell id="17" material="15" name="lead_shell" region="13 -14 10 -11" universe="10" />
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<cell id="18" material="14" name="matrix coolant surround" region="14 10 -11" universe="10" />
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<cell id="19" material="14" universe="11" />
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<cell fill="12" id="20" name="container cell" region="-15 16 -17 18 19 -20 10 -11" universe="13" />
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<hex_lattice id="12" n_rings="2" name="regular fuel assembly">
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<pitch>1.4</pitch>
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<outer>11</outer>
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<center>0.0 0.0</center>
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<universes>
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10
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10 10
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9
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10 10
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10</universes>
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</hex_lattice>
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<surface coeffs="0.0 0.0 0.7" id="9" type="z-cylinder" />
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<surface boundary="reflective" coeffs="0.0" id="10" type="z-plane" />
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<surface boundary="reflective" coeffs="10.0" id="11" type="z-plane" />
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<surface coeffs="0.0 0.0 0.293" id="12" type="z-cylinder" />
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<surface coeffs="0.0 0.0 0.35" id="13" type="z-cylinder" />
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<surface coeffs="0.0 0.0 0.352" id="14" type="z-cylinder" />
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<surface boundary="reflective" coeffs="1.4" id="15" type="y-plane" />
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<surface boundary="reflective" coeffs="-1.4" id="16" type="y-plane" />
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<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 2.8" id="17" type="plane" />
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<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 -2.8" id="18" type="plane" />
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<surface boundary="reflective" coeffs="1.7320508075688772 1.0 0.0 -2.8" id="19" type="plane" />
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<surface boundary="reflective" coeffs="-1.7320508075688772 1.0 0.0 2.8" id="20" type="plane" />
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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="13">
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<density units="sum" />
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<nuclide ao="0.0049817" name="U235" />
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</material>
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<material id="14">
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<density units="atom/b-cm" value="0.087742" />
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<nuclide ao="1.0" name="C0" />
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<sab name="c_Graphite" />
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</material>
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<material id="15" name="Lead">
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<density units="g/cm3" value="10.32" />
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<nuclide ao="0.014" name="Pb204" />
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<nuclide ao="0.241" name="Pb206" />
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<nuclide ao="0.221" name="Pb207" />
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<nuclide ao="0.524" name="Pb208" />
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</material>
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<material id="16">
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<density units="atom/b-cm" value="0.00054464" />
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<nuclide ao="1.0" name="He4" />
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</material>
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<material id="17" name="Zirc4">
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<density units="sum" />
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<nuclide ao="0.02217" name="Zr90" />
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<nuclide ao="0.004781" name="Zr91" />
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<nuclide ao="0.007228" name="Zr92" />
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<nuclide ao="0.007169" name="Zr94" />
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<nuclide ao="0.001131" name="Zr96" />
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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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<settings>
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<run_mode>eigenvalue</run_mode>
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<particles>1000</particles>
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<batches>10</batches>
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<inactive>5</inactive>
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<source strength="1.0">
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<space type="box">
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<parameters>-0.9899494936611666 -0.9899494936611666 0.0 0.9899494936611666 0.9899494936611666 10.0</parameters>
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</space>
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</source>
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<output>
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<summary>false</summary>
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</output>
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<seed>22</seed>
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</settings>
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@ -1,31 +0,0 @@
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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">
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<density units="sum" />
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<nuclide ao="0.0049817" name="U235" />
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</material>
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<material id="2">
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<density units="atom/b-cm" value="0.087742" />
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<nuclide ao="1.0" name="C0" />
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<sab name="c_Graphite" />
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</material>
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<material id="4">
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<density units="g/cm3" value="10.32" />
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<nuclide ao="0.014" name="Pb204" />
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<nuclide ao="0.241" name="Pb206" />
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<nuclide ao="0.221" name="Pb207" />
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<nuclide ao="0.524" name="Pb208" />
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</material>
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<material id="6">
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<density units="atom/b-cm" value="0.00054464" />
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<nuclide ao="1.0" name="He4" />
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</material>
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<material id="7">
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<density units="sum" />
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<nuclide ao="0.02217" name="Zr90" />
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<nuclide ao="0.004781" name="Zr91" />
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<nuclide ao="0.007228" name="Zr92" />
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<nuclide ao="0.007169" name="Zr94" />
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<nuclide ao="0.001131" name="Zr96" />
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</material>
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</materials>
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@ -1,16 +0,0 @@
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<?xml version='1.0' encoding='utf-8'?>
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<settings>
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<run_mode>eigenvalue</run_mode>
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<particles>1000</particles>
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<batches>10</batches>
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<inactive>5</inactive>
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<source strength="1.0">
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<space type="box">
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<parameters>-0.9899494936611666 -0.9899494936611666 0.0 0.9899494936611666 0.9899494936611666 10.0</parameters>
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</space>
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</source>
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<output>
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<summary>false</summary>
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</output>
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<seed>22</seed>
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</settings>
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@ -1,6 +1,150 @@
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from tests.testing_harness import TestHarness
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import numpy as np
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import openmc
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from tests.testing_harness import PyAPITestHarness
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class HexLatticeCoincidentTestHarness(PyAPITestHarness):
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def _build_inputs(self):
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materials = openmc.Materials()
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fuel_mat = openmc.Material()
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fuel_mat.add_nuclide('U235', 4.9817E-03, 'ao')
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materials.append(fuel_mat)
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matrix = openmc.Material()
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matrix.set_density('atom/b-cm', 8.7742E-02)
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matrix.add_element('C', 1.0, 'ao')
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matrix.add_s_alpha_beta('c_Graphite')
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materials.append(matrix)
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lead = openmc.Material(name="Lead")
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lead.set_density('g/cm3', 10.32)
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lead.add_nuclide('Pb204', 0.014, 'ao')
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lead.add_nuclide('Pb206', 0.241, 'ao')
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lead.add_nuclide('Pb207', 0.221, 'ao')
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lead.add_nuclide('Pb208', 0.524, 'ao')
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materials.append(lead)
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coolant = openmc.Material()
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coolant.set_density('atom/b-cm', 5.4464E-04)
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coolant.add_nuclide('He4', 1.0, 'ao')
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materials.append(coolant)
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zirc = openmc.Material(name="Zirc4")
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zirc.add_nuclide('Zr90', 2.217E-02, 'ao')
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zirc.add_nuclide('Zr91', 4.781E-03, 'ao')
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zirc.add_nuclide('Zr92', 7.228E-03, 'ao')
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zirc.add_nuclide('Zr94', 7.169E-03, 'ao')
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zirc.add_nuclide('Zr96', 1.131E-03, 'ao')
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materials.append(zirc)
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materials.export_to_xml()
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### Geometry ###
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pin_rad = 0.7 # cm
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assembly_pitch = 1.4 # cm
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cool_rad = 0.293 # cm
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zirc_clad_thickness = 0.057 # cm
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zirc_ir = cool_rad # cm
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zirc_or = cool_rad + zirc_clad_thickness # cm
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lead_thickness = 0.002 # cm
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lead_ir = zirc_or # cm
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lead_or = zirc_or + lead_thickness # cm
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cyl = openmc.ZCylinder(x0=0., y0=0., r=pin_rad)
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fuel_btm = openmc.ZPlane(z0=0.0, boundary_type = 'reflective')
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fuel_top = openmc.ZPlane(z0=10.0, boundary_type = 'reflective')
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region = -cyl & +fuel_btm & -fuel_top
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container = openmc.Cell(region=region)
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container.fill = fuel_mat
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fuel_outside = openmc.Cell()
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fuel_outside.region = +cyl
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fuel_outside.fill = matrix
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fuel_ch_univ = openmc.Universe(cells=[container, fuel_outside])
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# Coolant Channel
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cool_outer = openmc.ZCylinder(x0=0.0, y0=0.0, r=cool_rad)
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zirc_outer = openmc.ZCylinder(x0=0.0, y0=0.0, r=zirc_or)
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lead_outer = openmc.ZCylinder(x0=0.0, y0=0.0, r=lead_or)
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coolant_ch = openmc.Cell(name="coolant")
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coolant_ch.region = -cool_outer & +fuel_btm & -fuel_top
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coolant_ch.fill = coolant
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zirc_shell = openmc.Cell(name="zirconium_shell")
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zirc_shell.region = +cool_outer & -zirc_outer & +fuel_btm & -fuel_top
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zirc_shell.fill = zirc
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lead_shell = openmc.Cell(name="lead_shell")
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lead_shell.region = +zirc_outer & -lead_outer & +fuel_btm & -fuel_top
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lead_shell.fill = lead
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coolant_matrix = openmc.Cell(name="matrix coolant surround")
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coolant_matrix.region = +lead_outer & +fuel_btm & -fuel_top
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coolant_matrix.fill = matrix
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coolant_channel = [coolant_ch, zirc_shell, lead_shell, coolant_matrix]
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coolant_univ = openmc.Universe(name="coolant universe")
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coolant_univ.add_cells(coolant_channel)
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half_width = assembly_pitch # cm
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edge_length = (2./np.sqrt(3.0)) * half_width
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inf_mat = openmc.Cell()
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inf_mat.fill = matrix
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inf_mat_univ = openmc.Universe(cells=[inf_mat,])
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# a hex surface for the core to go inside of
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hexprism = openmc.model.get_hexagonal_prism(edge_length=edge_length,
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origin=(0.0, 0.0),
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boundary_type = 'reflective',
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orientation='x')
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pincell_only_lattice = openmc.HexLattice(name="regular fuel assembly")
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pincell_only_lattice.center = (0., 0.)
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pincell_only_lattice.pitch = (assembly_pitch,)
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pincell_only_lattice.outer = inf_mat_univ
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# setup hex rings
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ring0 = [fuel_ch_univ]
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ring1 = [coolant_univ] * 6
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pincell_only_lattice.universes = [ring1, ring0]
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pincell_only_cell = openmc.Cell(name="container cell")
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pincell_only_cell.region = hexprism & +fuel_btm & -fuel_top
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pincell_only_cell.fill = pincell_only_lattice
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root_univ = openmc.Universe(name="root universe", cells=[pincell_only_cell,])
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geom = openmc.Geometry(root_univ)
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geom.export_to_xml()
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### Settings ###
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settings = openmc.Settings()
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settings.run_mode = 'eigenvalue'
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source = openmc.Source()
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corner_dist = np.sqrt(2) * pin_rad
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ll = [-corner_dist, -corner_dist, 0.0]
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ur = [corner_dist, corner_dist, 10.0]
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source.space = openmc.stats.Box(ll, ur)
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source.strength = 1.0
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settings.source = source
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settings.output = {'summary' : False}
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settings.batches = 10
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settings.inactive = 5
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settings.particles = 1000
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settings.seed = 22
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settings.export_to_xml()
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def test_lattice_hex_coincident_surf():
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harness = TestHarness('statepoint.10.h5')
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harness = HexLatticeCoincidentTestHarness('statepoint.10.h5')
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harness.main()
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