mirror of
https://github.com/openmc-dev/openmc.git
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112 lines
4.8 KiB
XML
112 lines
4.8 KiB
XML
<?xml version='1.0' encoding='utf-8'?>
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<model>
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<materials>
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<cross_sections>mgxs.h5</cross_sections>
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<material id="1" name="UO2 fuel">
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<density value="1.0" units="macro"/>
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<macroscopic name="UO2"/>
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</material>
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<material id="2" name="Water">
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<density value="1.0" units="macro"/>
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<macroscopic name="LWTR"/>
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</material>
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</materials>
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<geometry>
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<cell id="1" name="fuel inner a" material="1" region="-2" universe="1"/>
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<cell id="2" name="fuel inner b" material="1" region="2 -3" universe="1"/>
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<cell id="3" name="fuel inner c" material="1" region="3 -1" universe="1"/>
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<cell id="4" name="moderator inner a" material="2" region="1 -4" universe="1"/>
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<cell id="5" name="moderator outer b" material="2" region="4 -5" universe="1"/>
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<cell id="6" name="moderator outer c" material="2" region="5" universe="1"/>
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<cell id="7" name="azimuthal_cell_0" fill="1" region="6 -7" universe="2"/>
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<cell id="8" name="azimuthal_cell_1" fill="1" region="7 -8" universe="2"/>
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<cell id="9" name="azimuthal_cell_2" fill="1" region="8 -9" universe="2"/>
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<cell id="10" name="azimuthal_cell_3" fill="1" region="9 -10" universe="2"/>
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<cell id="11" name="azimuthal_cell_4" fill="1" region="10 -11" universe="2"/>
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<cell id="12" name="azimuthal_cell_5" fill="1" region="11 -12" universe="2"/>
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<cell id="13" name="azimuthal_cell_6" fill="1" region="12 -13" universe="2"/>
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<cell id="14" name="azimuthal_cell_7" fill="1" region="13 -6" universe="2"/>
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<cell id="15" name="moderator infinite" material="2" universe="3"/>
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<cell id="16" fill="4" universe="5"/>
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<cell id="17" name="assembly" fill="6" region="14 -15 16 -17" universe="7"/>
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<lattice id="4">
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<pitch>0.126 0.126</pitch>
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<dimension>10 10</dimension>
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<lower_left>-0.63 -0.63</lower_left>
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<universes>
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3 3 3 3 3 3 3 3 3 3
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3 3 3 3 3 3 3 3 3 3
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3 3 3 3 3 3 3 3 3 3
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3 3 3 3 3 3 3 3 3 3
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3 3 3 3 3 3 3 3 3 3
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3 3 3 3 3 3 3 3 3 3
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3 3 3 3 3 3 3 3 3 3
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3 3 3 3 3 3 3 3 3 3
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3 3 3 3 3 3 3 3 3 3
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3 3 3 3 3 3 3 3 3 3 </universes>
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</lattice>
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<lattice id="6">
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<pitch>1.26 1.26</pitch>
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<dimension>2 2</dimension>
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<lower_left>-1.26 -1.26</lower_left>
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<universes>
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2 2
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2 5 </universes>
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</lattice>
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<surface id="1" name="Fuel OR" type="z-cylinder" coeffs="0.0 0.0 0.54"/>
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<surface id="2" name="inner ring a" type="z-cylinder" coeffs="0.0 0.0 0.33"/>
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<surface id="3" name="inner ring b" type="z-cylinder" coeffs="0.0 0.0 0.45"/>
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<surface id="4" name="outer ring a" type="z-cylinder" coeffs="0.0 0.0 0.6"/>
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<surface id="5" name="outer ring b" type="z-cylinder" coeffs="0.0 0.0 0.69"/>
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<surface id="6" type="plane" coeffs="-0.0 1.0 0 0"/>
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<surface id="7" type="plane" coeffs="-0.7071067811865475 0.7071067811865476 0 0"/>
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<surface id="8" type="plane" coeffs="-1.0 6.123233995736766e-17 0 0"/>
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<surface id="9" type="plane" coeffs="-0.7071067811865476 -0.7071067811865475 0 0"/>
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<surface id="10" type="plane" coeffs="-1.2246467991473532e-16 -1.0 0 0"/>
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<surface id="11" type="plane" coeffs="0.7071067811865475 -0.7071067811865477 0 0"/>
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<surface id="12" type="plane" coeffs="1.0 -1.8369701987210297e-16 0 0"/>
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<surface id="13" type="plane" coeffs="0.7071067811865477 0.7071067811865474 0 0"/>
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<surface id="14" name="minimum x" type="x-plane" boundary="reflective" coeffs="-1.26"/>
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<surface id="15" name="maximum x" type="x-plane" boundary="reflective" coeffs="1.26"/>
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<surface id="16" name="minimum y" type="y-plane" boundary="reflective" coeffs="-1.26"/>
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<surface id="17" name="maximum y" type="y-plane" boundary="reflective" coeffs="1.26"/>
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</geometry>
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<settings>
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<run_mode>eigenvalue</run_mode>
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<particles>100</particles>
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<batches>40</batches>
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<inactive>20</inactive>
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<energy_mode>multi-group</energy_mode>
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<random_ray>
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<distance_active>100.0</distance_active>
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<distance_inactive>20.0</distance_inactive>
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<ray_source>
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<source type="independent" strength="1.0" particle="neutron">
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<space type="box">
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<parameters>-1.26 -1.26 -1 1.26 1.26 1</parameters>
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</space>
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</source>
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</ray_source>
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<volume_normalized_flux_tallies>true</volume_normalized_flux_tallies>
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<source_shape>linear</source_shape>
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</random_ray>
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</settings>
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<tallies>
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<mesh id="1">
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<dimension>2 2</dimension>
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<lower_left>-1.26 -1.26</lower_left>
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<upper_right>1.26 1.26</upper_right>
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</mesh>
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<filter id="1" type="mesh">
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<bins>1</bins>
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</filter>
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<filter id="2" type="energy">
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<bins>1e-05 0.0635 10.0 100.0 1000.0 500000.0 1000000.0 20000000.0</bins>
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</filter>
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<tally id="1" name="Mesh tally">
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<filters>1 2</filters>
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<scores>flux fission nu-fission</scores>
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<estimator>analog</estimator>
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</tally>
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</tallies>
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</model>
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