mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-25 20:45:35 -04:00
Fixed p%coord(?) bug where i had the wrong coordinate index, showed up in the c5g7 problems with their lattices and thus n_coord was not 1. Also added c5g7 example problems.
This commit is contained in:
Adam Nelson
parent
7497efb153
commit
39445f059f
20 changed files with 1054 additions and 6 deletions
20
examples/xml/multigroup/c5g7/2d/cmfd.xml
Normal file
20
examples/xml/multigroup/c5g7/2d/cmfd.xml
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@ -0,0 +1,20 @@
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<?xml version="1.0"?>
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<cmfd>
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<begin>1</begin>
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<feedback>true</feedback>
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<solver>jfnk</solver>
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<mesh>
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<lower_left> 0.0 0.0 -100.0</lower_left>
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<upper_right> 64.26 64.26 100.0</upper_right>
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<dimension>6 6 1</dimension>
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<map>
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2 2 2 2 1 1
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2 2 2 2 1 1
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2 2 2 2 1 1
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2 2 2 2 1 1
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1 1 1 1 1 1
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1 1 1 1 1 1
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</map>
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</mesh>
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</cmfd>
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118
examples/xml/multigroup/c5g7/2d/geometry.xml
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118
examples/xml/multigroup/c5g7/2d/geometry.xml
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@ -0,0 +1,118 @@
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<geometry>
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<surface coeffs="0. 0. 0.540" id="1" type="z-cylinder" />
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<surface boundary="reflective" coeffs=" 0.0" id="20" type="x-plane" />
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<surface boundary="vacuum" coeffs=" 64.26" id="21" type="x-plane" />
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<surface boundary="vacuum" coeffs=" 0.0" id="22" type="y-plane" />
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<surface boundary="reflective" coeffs=" 64.26" id="23" type="y-plane" />
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<surface boundary="reflective" coeffs="-100.0" id="35" type="z-plane" />
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<surface boundary="reflective" coeffs=" 100.0" id="36" type="z-plane" />
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<cell id="10" material="1" region="-1" universe="1" />
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<cell id="11" material="7" region=" 1" universe="1" />
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<cell id="20" material="2" region="-1" universe="2" />
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<cell id="21" material="7" region=" 1" universe="2" />
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<cell id="30" material="3" region="-1" universe="3" />
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<cell id="31" material="7" region=" 1" universe="3" />
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<cell id="40" material="4" region="-1" universe="4" />
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<cell id="41" material="7" region=" 1" universe="4" />
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<cell id="50" material="5" region="-1" universe="5" />
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<cell id="51" material="7" region=" 1" universe="5" />
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<cell id="60" material="6" region="-1" universe="6" />
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<cell id="61" material="7" region=" 1" universe="6" />
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<lattice id="100">
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<outer>0</outer>
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<dimension>17 17</dimension>
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<lower_left>-10.71 -10.71</lower_left>
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<pitch>1.26 1.26</pitch>
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<universes>
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 6 1 1 6 1 1 6 1 1 1 1 1
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1 1 1 6 1 1 1 1 1 1 1 1 1 6 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 6 1 1 6 1 1 6 1 1 6 1 1 6 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 6 1 1 6 1 1 5 1 1 6 1 1 6 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 6 1 1 6 1 1 6 1 1 6 1 1 6 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 6 1 1 1 1 1 1 1 1 1 6 1 1 1
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1 1 1 1 1 6 1 1 6 1 1 6 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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</universes>
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</lattice>
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<lattice id="101">
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<outer>0</outer>
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<dimension>17 17</dimension>
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<lower_left>-10.71 -10.71</lower_left>
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<pitch>1.26 1.26</pitch>
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<universes>
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
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2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2
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2 3 3 3 3 6 3 3 6 3 3 6 3 3 3 3 2
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2 3 3 6 3 4 4 4 4 4 4 4 3 6 3 3 2
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2 3 3 3 4 4 4 4 4 4 4 4 4 3 3 3 2
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2 3 6 4 4 6 4 4 6 4 4 6 4 4 6 3 2
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2 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 2
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2 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 2
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2 3 6 4 4 6 4 4 5 4 4 6 4 4 6 3 2
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2 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 2
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2 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 2
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2 3 6 4 4 6 4 4 6 4 4 6 4 4 6 3 2
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2 3 3 3 4 4 4 4 4 4 4 4 4 3 3 3 2
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2 3 3 6 3 4 4 4 4 4 4 4 3 6 3 3 2
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2 3 3 3 3 6 3 3 6 3 3 6 3 3 3 3 2
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2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
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</universes>
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</lattice>
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<cell id="112" material="7" region="35 -36" universe="12" />
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<cell fill="100" id="110" region="35 -36" universe="10" />
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<cell fill="101" id="111" region="35 -36" universe="11" />
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<lattice id="200">
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<outer>0</outer>
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<dimension>3 3</dimension>
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<lower_left>0.0 0.0</lower_left>
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<pitch>21.42 21.42</pitch>
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<universes>
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10 11 12
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11 10 12
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12 12 12
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</universes>
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</lattice>
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<cell fill="200" id="1" region=" 20 -21 22 -23 35 -36" />
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</geometry>
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1
examples/xml/multigroup/c5g7/2d/materials.xml
Symbolic link
1
examples/xml/multigroup/c5g7/2d/materials.xml
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@ -0,0 +1 @@
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/home/nelsonag/cases/c5g7/materials.xml
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29
examples/xml/multigroup/c5g7/2d/plots.xml
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29
examples/xml/multigroup/c5g7/2d/plots.xml
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@ -0,0 +1,29 @@
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<?xml version="1.0"?>
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<plots>
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<plot>
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<id>1</id>
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<filename>mat</filename>
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<color>material</color>
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<origin>32.13 32.13 0</origin>
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<width>64.26 64.26</width>
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<type>slice</type>
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<pixels>1000 1000 </pixels>
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<!-- <col_spec id="1" rgb="255 0 0" />
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<col_spec id="2" rgb="0 0 0" />
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<col_spec id="3" rgb="0 255 0" />
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<col_spec id="4" rgb="0 0 255" />
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-->
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</plot>
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<plot>
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<id>2</id>
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<filename>cell</filename>
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<color>cell</color>
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<origin>32.13 32.13 0</origin>
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<width>64.26 64.26</width>
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<type>slice</type>
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<pixels>1000 1000 </pixels>
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</plot>
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</plots>
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50
examples/xml/multigroup/c5g7/2d/settings.xml
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50
examples/xml/multigroup/c5g7/2d/settings.xml
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@ -0,0 +1,50 @@
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<?xml version="1.0"?>
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<settings>
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<energy_mode>multi-group</energy_mode>
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<!--
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Define how many particles to run and for how many batches
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in an eigenvalue calculation mode
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-->
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<eigenvalue>
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<batches>2500</batches>
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<inactive>500</inactive>
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<particles> 1000 </particles>
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</eigenvalue>
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<uniform_fs>
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<lower_left> 0.0 21.42 -100 </lower_left>
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<upper_right> 42.84 64.26 100 </upper_right>
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<dimension> 34 34 1 </dimension>
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</uniform_fs>
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<!--
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Start with uniformally distributed neutron source
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with the default energy spectrum of a Maxwellian
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and isotropic distribution.
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-->
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<source>
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<space type="box">
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<parameters>
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0.0 21.42 -100
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42.84 64.26 100
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</parameters>
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</space>
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</source>
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<!-- Establish statepoints to aid in examining convergence -->
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<state_point>
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<interval> 2000 </interval>
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<source_write>true</source_write>
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</state_point>
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<output>
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<cross_sections>true</cross_sections>
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<summary>true</summary>
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<tallies>true</tallies>
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</output>
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<run_cmfd>false</run_cmfd>
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<cross_sections>../data.xml</cross_sections>
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</settings>
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25
examples/xml/multigroup/c5g7/2d/tallies.xml
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25
examples/xml/multigroup/c5g7/2d/tallies.xml
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<?xml version="1.0"?>
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<tallies>
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<tally id="1">
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<filter type="mesh" bins="1" />
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<filter type="energy" />
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<scores>flux</scores>
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</tally>
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<tally id="2">
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<filter type="mesh" bins="1"/>
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<scores>fission</scores>
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</tally>
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<mesh>
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<id>1</id>
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<type>regular</type>
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<lower_left> 0.0 0.0 -100.0 </lower_left>
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<upper_right> 64.26 64.26 100.0 </upper_right>
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<dimension> 51 51 1 </dimension>
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</mesh>
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<assume_separate>false</assume_separate>
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</tallies>
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138
examples/xml/multigroup/c5g7/3d/geometry.xml
Normal file
138
examples/xml/multigroup/c5g7/3d/geometry.xml
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@ -0,0 +1,138 @@
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<geometry>
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<surface coeffs="0. 0. 0.540" id="1" type="z-cylinder" />
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<surface boundary="reflective" coeffs=" 0.0" id="20" type="x-plane" />
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<surface boundary="vacuum" coeffs=" 64.26" id="21" type="x-plane" />
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<surface boundary="vacuum" coeffs=" 0.0" id="22" type="y-plane" />
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<surface boundary="reflective" coeffs=" 64.26" id="23" type="y-plane" />
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<surface boundary="reflective" coeffs=" 0.0" id="30" type="z-plane" />
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<surface coeffs="192.78" id="31" type="z-plane" />
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<surface boundary="vacuum" coeffs=" 214.2" id="32" type="z-plane" />
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<cell id="10" material="1" region="-1" universe="1" />
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<cell id="11" material="7" region=" 1" universe="1" />
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<cell id="20" material="2" region="-1" universe="2" />
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<cell id="21" material="7" region=" 1" universe="2" />
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<cell id="30" material="3" region="-1" universe="3" />
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<cell id="31" material="7" region=" 1" universe="3" />
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<cell id="40" material="4" region="-1" universe="4" />
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<cell id="41" material="7" region=" 1" universe="4" />
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<cell id="50" material="5" region="-1" universe="5" />
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<cell id="51" material="7" region=" 1" universe="5" />
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<cell id="60" material="6" region="-1" universe="6" />
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<cell id="61" material="7" region=" 1" universe="6" />
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<lattice id="100">
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<outer>0</outer>
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<dimension>17 17</dimension>
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<lower_left>-10.71 -10.71</lower_left>
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<pitch>1.26 1.26</pitch>
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<universes>
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 6 1 1 6 1 1 6 1 1 1 1 1
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1 1 1 6 1 1 1 1 1 1 1 1 1 6 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 6 1 1 6 1 1 6 1 1 6 1 1 6 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 6 1 1 6 1 1 5 1 1 6 1 1 6 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 6 1 1 6 1 1 6 1 1 6 1 1 6 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 6 1 1 1 1 1 1 1 1 1 6 1 1 1
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1 1 1 1 1 6 1 1 6 1 1 6 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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</universes>
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</lattice>
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<lattice id="101">
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<outer>0</outer>
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<dimension>17 17</dimension>
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<lower_left>-10.71 -10.71</lower_left>
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<pitch>1.26 1.26</pitch>
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<universes>
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
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2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2
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2 3 3 3 3 6 3 3 6 3 3 6 3 3 3 3 2
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||||
2 3 3 6 3 4 4 4 4 4 4 4 3 6 3 3 2
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||||
2 3 3 3 4 4 4 4 4 4 4 4 4 3 3 3 2
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||||
2 3 6 4 4 6 4 4 6 4 4 6 4 4 6 3 2
|
||||
2 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 2
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||||
2 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 2
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2 3 6 4 4 6 4 4 5 4 4 6 4 4 6 3 2
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||||
2 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 2
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||||
2 3 3 4 4 4 4 4 4 4 4 4 4 4 3 3 2
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||||
2 3 6 4 4 6 4 4 6 4 4 6 4 4 6 3 2
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||||
2 3 3 3 4 4 4 4 4 4 4 4 4 3 3 3 2
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||||
2 3 3 6 3 4 4 4 4 4 4 4 3 6 3 3 2
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2 3 3 3 3 6 3 3 6 3 3 6 3 3 3 3 2
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2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 2
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
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</universes>
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</lattice>
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<cell id="112" material="7" region="30 -31" universe="12" />
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|
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<cell fill="100" id="110" region="30 -31" universe="10" />
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|
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|
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<cell fill="101" id="111" region="30 -31" universe="11" />
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|
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|
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<lattice id="200" outer="199">
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||||
|
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<dimension>3 3</dimension>
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<lower_left>0.0 0.0</lower_left>
|
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<pitch>21.42 21.42</pitch>
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<universes>
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10 11 12
|
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11 10 12
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12 12 12
|
||||
</universes>
|
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</lattice>
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|
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<cell fill="200" id="1" region=" 20 -21 22 -23 30 -31" />
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|
||||
|
||||
|
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<cell id="113" material="7" region="31 -32" universe="13" />
|
||||
|
||||
<lattice id="201" outer="202">
|
||||
|
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<dimension>3 3</dimension>
|
||||
<lower_left>0.0 0.0</lower_left>
|
||||
<pitch>21.42 21.42</pitch>
|
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<universes>
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||||
13 13 13
|
||||
13 13 13
|
||||
13 13 13
|
||||
</universes>
|
||||
</lattice>
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||||
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<cell fill="201" id="2" region=" 20 -21 22 -23 31 -32" />
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<cell id="199" material="void" universe="199" /><cell id="202" material="void" universe="202" /></geometry>
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1
examples/xml/multigroup/c5g7/3d/materials.xml
Symbolic link
1
examples/xml/multigroup/c5g7/3d/materials.xml
Symbolic link
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../materials.xml
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42
examples/xml/multigroup/c5g7/3d/plots.xml
Normal file
42
examples/xml/multigroup/c5g7/3d/plots.xml
Normal file
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@ -0,0 +1,42 @@
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<?xml version="1.0"?>
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<plots>
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<plot>
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<id>1</id>
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<filename>mat</filename>
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<color>material</color>
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<origin>32.13 32.13 107.1</origin>
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<width>64.26 214.2</width>
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<type>slice</type>
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<pixels>1000 1000 </pixels>
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<!-- <col_spec id="1" rgb="255 0 0" />
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<col_spec id="2" rgb="0 0 0" />
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<col_spec id="3" rgb="0 255 0" />
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<col_spec id="4" rgb="0 0 255" />
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-->
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<basis>xz</basis>
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</plot>
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<plot>
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<id>2</id>
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<filename>cell</filename>
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<color>cell</color>
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<origin>32.13 32.13 107.1</origin>
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<width>64.26 214.2</width>
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||||
<type>slice</type>
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<pixels>1000 1000 </pixels>
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<basis>xz</basis>
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</plot>
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<plot>
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||||
<id>3</id>
|
||||
<filename>mat_xy</filename>
|
||||
<color>material</color>
|
||||
<origin>32.13 32.13 107.1</origin>
|
||||
<width>64.26 64.26</width>
|
||||
<type>slice</type>
|
||||
<pixels>1000 1000 </pixels>
|
||||
<basis>xy</basis>
|
||||
</plot>
|
||||
|
||||
</plots>
|
||||
49
examples/xml/multigroup/c5g7/3d/settings.xml
Normal file
49
examples/xml/multigroup/c5g7/3d/settings.xml
Normal file
|
|
@ -0,0 +1,49 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
<energy_mode>multi-group</energy_mode>
|
||||
<!--
|
||||
Define how many particles to run and for how many batches
|
||||
in an eigenvalue calculation mode
|
||||
-->
|
||||
<eigenvalue>
|
||||
<batches>2000</batches>
|
||||
<inactive>500</inactive>
|
||||
<particles>1000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<uniform_fs>
|
||||
<lower_left> 0.0 21.42 0.0 </lower_left>
|
||||
<upper_right> 42.84 64.26 192.78 </upper_right>
|
||||
<dimension> 34 34 54 </dimension>
|
||||
</uniform_fs>
|
||||
|
||||
<!--
|
||||
Start with uniformally distributed neutron source
|
||||
with the default energy spectrum of a Maxwellian
|
||||
and isotropic distribution.
|
||||
-->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>
|
||||
0.0 21.42 0.0
|
||||
42.84 64.26 192.78
|
||||
</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
<!-- Establish statepoints -->
|
||||
<state_point>
|
||||
<interval>2000</interval>
|
||||
</state_point>
|
||||
|
||||
<output>
|
||||
<cross_sections>true</cross_sections>
|
||||
<summary>true</summary>
|
||||
<tallies>true</tallies>
|
||||
</output>
|
||||
|
||||
<run_cmfd>false</run_cmfd>
|
||||
|
||||
<cross_sections>../data.xml</cross_sections>
|
||||
|
||||
</settings>
|
||||
33
examples/xml/multigroup/c5g7/3d/tallies.xml
Normal file
33
examples/xml/multigroup/c5g7/3d/tallies.xml
Normal file
|
|
@ -0,0 +1,33 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
||||
<filter type="energy" />
|
||||
<scores>flux</scores>
|
||||
</tally>
|
||||
|
||||
<tally id="2">
|
||||
<filter type="mesh" bins="2"/>
|
||||
<scores>fission</scores>
|
||||
</tally>
|
||||
|
||||
<mesh>
|
||||
<id>1</id>
|
||||
<type>rectangular</type>
|
||||
<lower_left> 0.0 0.0 0.0 </lower_left>
|
||||
<upper_right> 64.26 64.26 214.2 </upper_right>
|
||||
<dimension> 51 51 60 </dimension>
|
||||
</mesh>
|
||||
|
||||
<mesh>
|
||||
<id>2</id>
|
||||
<type>rectangular</type>
|
||||
<lower_left> 0.0 21.42 0.0 </lower_left>
|
||||
<upper_right> 42.84 64.26 192.78 </upper_right>
|
||||
<dimension> 34 34 54 </dimension>
|
||||
</mesh>
|
||||
|
||||
<assume_separate>false</assume_separate>
|
||||
|
||||
</tallies>
|
||||
383
examples/xml/multigroup/c5g7/data.xml
Normal file
383
examples/xml/multigroup/c5g7/data.xml
Normal file
|
|
@ -0,0 +1,383 @@
|
|||
<?xml version="1.0"?>
|
||||
<library>
|
||||
<!-- Before getting to the data, set common information -->
|
||||
<groups> 7 </groups>
|
||||
<group_structure>
|
||||
1E-11 0.0635E-6 10.0E-6 1.0E-4 1.0E-3 0.5 1.0 20.0
|
||||
</group_structure>
|
||||
|
||||
<!--
|
||||
Move on to the data. Each <xsdata> has a unique id and label.
|
||||
-->
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>UO2.71c</name>
|
||||
<alias>UO2.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>true</fissionable>
|
||||
<!-- Optional (default is isotropic) -->
|
||||
<representation>isotropic</representation>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
8.0248E-03 3.7174E-03 2.6769E-02 9.6236E-02 3.0020E-02 1.1126E-01 2.8278E-01
|
||||
</absorption>
|
||||
|
||||
<nu_fission>
|
||||
2.005998E-02 2.027303E-03 1.570599E-02 4.518301E-02 4.334208E-02 2.020901E-01 5.257105E-01
|
||||
</nu_fission>
|
||||
|
||||
<chi>
|
||||
5.8791E-01 4.1176E-01 3.3906E-04 1.1761E-07 0.0000E+00 0.0000E+00 0.0000E+00
|
||||
</chi>
|
||||
<fission>
|
||||
7.21206E-03 8.19301E-04 6.45320E-03 1.85648E-02 1.78084E-02 8.30348E-02 2.16004E-01
|
||||
</fission>
|
||||
|
||||
<!-- units of MeV/cm -->
|
||||
<!-- If no kappa fission tallies, this is not needed; it will not be loaded
|
||||
if there is no kappa fission scores anyways -->
|
||||
<k_fission>
|
||||
1.0 1.0 1.0 1.0 1.0 1.0 1.0
|
||||
</k_fission>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
0.1275370 0.0423780 0.0000094 0.0000000 0.0000000 0.0000000 0.0000000
|
||||
0.0000000 0.3244560 0.0016314 0.0000000 0.0000000 0.0000000 0.0000000
|
||||
0.0000000 0.0000000 0.4509400 0.0026792 0.0000000 0.0000000 0.0000000
|
||||
0.0000000 0.0000000 0.0000000 0.4525650 0.0055664 0.0000000 0.0000000
|
||||
0.0000000 0.0000000 0.0000000 0.0001253 0.2714010 0.0102550 0.0000000
|
||||
0.0000000 0.0000000 0.0000000 0.0000000 0.0012968 0.2658020 0.0168090
|
||||
0.0000000 0.0000000 0.0000000 0.0000000 0.0000000 0.0085458 0.2730800
|
||||
</scatter>
|
||||
|
||||
<!-- If total is not provided, it will be calculated.
|
||||
However, in the C5G7 problems, we want to use a transport-corrected value
|
||||
so we dont want to have it be calculated -->
|
||||
<total>
|
||||
0.1779492 0.3298048 0.4803882 0.5543674000000001 0.3118013 0.39516779999999996 0.5644058
|
||||
</total>
|
||||
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>MOX1.71c</name>
|
||||
<alias>MOX1.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>true</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
8.4339E-03 3.7577E-03 2.7970E-02 1.0421E-01 1.3994E-01 4.0918E-01 4.0935E-01
|
||||
</absorption>
|
||||
<!--
|
||||
Since chi_vector is false, this will be a matrix
|
||||
Matrix is g_in, g_out.
|
||||
This is to show that you can either use a chi vector + nu_fission vector,
|
||||
like in the UO2 data, or a nu_fission matrix like here.
|
||||
-->
|
||||
<nu_fission>
|
||||
1.27888062E-02 8.95701528E-03 7.37557218E-06 2.55837033E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
1.49041240E-03 1.04385401E-03 8.59552023E-07 2.98153464E-10 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
9.56411400E-03 6.69850756E-03 5.51582469E-06 1.91327830E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
3.84928781E-02 2.69596154E-02 2.21996483E-05 7.70040890E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
1.80629998E-02 1.26509513E-02 1.04173100E-05 3.61346022E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
3.91930789E-01 2.74500216E-01 2.26034688E-04 7.84048241E-08 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
4.19762096E-01 2.93992687E-01 2.42085585E-04 8.39724109E-08 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
</nu_fission>
|
||||
|
||||
<fission>
|
||||
7.62704E-03 8.76898E-04 5.69835E-03 2.28872E-02 1.07635E-02 2.32757E-01 2.48968E-01
|
||||
</fission>
|
||||
|
||||
<!-- units of MeV/cm -->
|
||||
<k_fission>
|
||||
1.0 1.0 1.0 1.0 1.0 1.0 1.0
|
||||
</k_fission>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
1.27537000E-01 4.23780000E-02 9.43740000E-06 5.51630000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 3.24456000E-01 1.63140000E-03 3.14270000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 4.50940000E-01 2.67920000E-03 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 4.52565000E-01 5.56640000E-03 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 1.25250000E-04 2.71401000E-01 1.02550000E-02 1.00210000E-08
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 1.29680000E-03 2.65802000E-01 1.68090000E-02
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 8.54580000E-03 2.73080000E-01
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
0.1783583429163 0.3298451031427 0.4815892 0.5623414 0.421721260021 0.6930878 0.6909757999999999
|
||||
</total>
|
||||
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>MOX2.71c</name>
|
||||
<alias>MOX2.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>true</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
0.0090657 0.0042967 0.032881 0.12203 0.18298 0.56846 0.58521
|
||||
</absorption>
|
||||
<!--
|
||||
Since chi_vector is false, this will be a matrix
|
||||
Matrix is g_in, g_out !!! Need to get these values looking right to match
|
||||
output of a nu-fission tally with <energy> filter above <energyout> filter
|
||||
-->
|
||||
<nu_fission>
|
||||
1.40004593E-02 9.80563205E-03 8.07435789E-06 2.80075866E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
2.26856185E-03 1.58885378E-03 1.30832709E-06 4.53820413E-10 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
1.41886199E-02 9.93741584E-03 8.18287404E-06 2.83839974E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
5.54788444E-02 3.88562347E-02 3.19958106E-05 1.10984111E-08 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
2.69085702E-02 1.88462058E-02 1.55187355E-05 5.38299559E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
5.45687127E-01 3.82187973E-01 3.14709185E-04 1.09163414E-07 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
6.13307712E-01 4.29548032E-01 3.53707392E-04 1.22690752E-07 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
</nu_fission>
|
||||
|
||||
<fission>
|
||||
0.00825446 0.00132565 0.00842156 0.032873 0.0159636 0.323794 0.362803
|
||||
</fission>
|
||||
|
||||
<!-- units of MeV/cm -->
|
||||
<k_fission>
|
||||
1.0 1.0 1.0 1.0 1.0 1.0 1.0
|
||||
</k_fission>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
1.30457000E-01 4.17920000E-02 8.51050000E-06 5.13290000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 3.28428000E-01 1.64360000E-03 2.20170000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 4.58371000E-01 2.53310000E-03 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 4.63709000E-01 5.47660000E-03 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 1.76190000E-04 2.82313000E-01 8.72890000E-03 9.00160000E-09
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 2.27600000E-03 2.49751000E-01 1.31140000E-02
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 8.86450000E-03 2.59529000E-01
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
0.1813232156329 0.3343683022017 0.4937851 0.5912156 0.47419809900160004 0.833601 0.8536035
|
||||
</total>
|
||||
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>MOX3.71c</name>
|
||||
<alias>MOX3.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>true</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
9.48620000E-03 4.65560000E-03 3.62400000E-02 1.32720000E-01 2.08400000E-01 6.58700000E-01 6.90170000E-01
|
||||
</absorption>
|
||||
<!--
|
||||
Since chi_vector is false, this will be a matrix
|
||||
Matrix is g_in, g_out !!! Need to get these values looking right to match
|
||||
output of a nu-fission tally with <energy> filter above <energyout> filter
|
||||
-->
|
||||
<nu_fission>
|
||||
1.48071013E-02 1.03705874E-02 8.53956516E-06 2.96212546E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
2.78640474E-03 1.95154023E-03 1.60697792E-06 5.57413653E-10 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
1.73304404E-02 1.21378819E-02 9.99482763E-06 3.46691346E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
6.59928975E-02 4.62200600E-02 3.80594850E-05 1.32017225E-08 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
3.25131926E-02 2.27715674E-02 1.87510386E-05 6.50418701E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
6.32002662E-01 4.42641588E-01 3.64489161E-04 1.26430632E-07 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
7.28595687E-01 5.10293344E-01 4.20196380E-04 1.45753838E-07 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
</nu_fission>
|
||||
|
||||
<fission>
|
||||
8.67209000E-03 1.62426000E-03 1.02716000E-02 3.90447000E-02 1.92576000E-02 3.74888000E-01 4.30599000E-01
|
||||
</fission>
|
||||
|
||||
<!-- units of MeV/cm -->
|
||||
<k_fission>
|
||||
1.0 1.0 1.0 1.0 1.0 1.0 1.0
|
||||
</k_fission>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
1.31504000E-01 4.20460000E-02 8.69720000E-06 5.19380000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 3.30403000E-01 1.64630000E-03 2.60060000E-09 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 4.61792000E-01 2.47490000E-03 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 4.68021000E-01 5.43300000E-03 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 1.85970000E-04 2.85771000E-01 8.39730000E-03 8.92800000E-09
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 2.39160000E-03 2.47614000E-01 1.23220000E-02
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 8.96810000E-03 2.56093000E-01
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
1.83044902E-01 3.36704903E-01 5.00506900E-01 6.06174000E-01 5.02754279E-01 9.21027600E-01 9.55231100E-01
|
||||
</total>
|
||||
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>FC.71c</name>
|
||||
<alias>FC.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>true</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
5.1132E-04 7.5813E-05 3.1643E-04 1.1675E-03 3.3977E-03 9.1886E-03 2.3244E-02
|
||||
</absorption>
|
||||
|
||||
<nu_fission>
|
||||
1.323401E-08 1.434500E-08 1.128599E-06 1.276299E-05 3.538502E-07 1.740099E-06 5.063302E-06
|
||||
</nu_fission>
|
||||
|
||||
<chi>
|
||||
5.8791E-01 4.1176E-01 3.3906E-04 1.1761E-07 0.0000E+00 0.0000E+00 0.0000E+00
|
||||
</chi>
|
||||
|
||||
<fission>
|
||||
4.79002E-09 5.82564E-09 4.63719E-07 5.24406E-06 1.45390E-07 7.14972E-07 2.08041E-06
|
||||
</fission>
|
||||
|
||||
<!-- units of MeV/cm -->
|
||||
<k_fission>
|
||||
1.0 1.0 1.0 1.0 1.0 1.0 1.0
|
||||
</k_fission>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
6.61659000E-02 5.90700000E-02 2.83340000E-04 1.46220000E-06 2.06420000E-08 0.00000000E00 0.00000000E00
|
||||
0.00000000E00 2.40377000E-01 5.24350000E-02 2.49900000E-04 1.92390000E-05 2.98750000E-06 4.21400000E-07
|
||||
0.00000000E00 0.00000000E00 1.83425000E-01 9.22880000E-02 6.93650000E-03 1.07900000E-03 2.05430000E-04
|
||||
0.00000000E00 0.00000000E00 0.00000000E00 7.90769000E-02 1.69990000E-01 2.58600000E-02 4.92560000E-03
|
||||
0.00000000E00 0.00000000E00 0.00000000E00 3.73400000E-05 9.97570000E-02 2.06790000E-01 2.44780000E-02
|
||||
0.00000000E00 0.00000000E00 0.00000000E00 0.00000000E00 9.17420000E-04 3.16774000E-01 2.38760000E-01
|
||||
0.00000000E00 0.00000000E00 0.00000000E00 0.00000000E00 0.00000000E00 4.97930000E-02 1.09910000E00
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
1.26032048E-01 2.93160367E-01 2.84250824E-01 2.81025244E-01 3.34460185E-01 5.65640735E-01 1.17213908E00
|
||||
</total>
|
||||
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>GT.71c</name>
|
||||
<alias>GT.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>false</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
5.11320000E-04 7.58010000E-05 3.15720000E-04 1.15820000E-03 3.39750000E-03 9.18780000E-03 2.32420000E-02
|
||||
</absorption>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
6.61659000E-02 5.90700000E-02 2.83340000E-04 1.46220000E-06 2.06420000E-08 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 2.40377000E-01 5.24350000E-02 2.49900000E-04 1.92390000E-05 2.98750000E-06 4.21400000E-07
|
||||
0.00000000E+00 0.00000000E+00 1.83297000E-01 9.23970000E-02 6.94460000E-03 1.08030000E-03 2.05670000E-04
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 7.88511000E-02 1.70140000E-01 2.58810000E-02 4.92970000E-03
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 3.73330000E-05 9.97372000E-02 2.06790000E-01 2.44780000E-02
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 9.17260000E-04 3.16765000E-01 2.38770000E-01
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 4.97920000E-02 1.09912000E+00
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
1.26032043E-01 2.93160349E-01 2.84240290E-01 2.80960000E-01 3.34440033E-01 5.65640060E-01 1.17215400E+00
|
||||
</total>
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>LWTR.71c</name>
|
||||
<alias>LWTR.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>false</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
6.0105E-04 1.5793E-05 3.3716E-04 1.9406E-03 5.7416E-03 1.5001E-02 3.7239E-02
|
||||
</absorption>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
0.0444777 0.1134000 0.0007235 0.0000037 0.0000001 0.0000000 0.0000000
|
||||
0.0000000 0.2823340 0.1299400 0.0006234 0.0000480 0.0000074 0.0000010
|
||||
0.0000000 0.0000000 0.3452560 0.2245700 0.0169990 0.0026443 0.0005034
|
||||
0.0000000 0.0000000 0.0000000 0.0910284 0.4155100 0.0637320 0.0121390
|
||||
0.0000000 0.0000000 0.0000000 0.0000714 0.1391380 0.5118200 0.0612290
|
||||
0.0000000 0.0000000 0.0000000 0.0000000 0.0022157 0.6999130 0.5373200
|
||||
0.0000000 0.0000000 0.0000000 0.0000000 0.0000000 0.1324400 2.4807000
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
0.15920605 0.41296959299999997 0.59030986 0.5843499999999999 0.7180000000000001 1.2544497000000001 2.650379
|
||||
</total>
|
||||
|
||||
</xsdata>
|
||||
|
||||
<xsdata>
|
||||
<!-- Meta data for this data -->
|
||||
<name>CR.71c</name>
|
||||
<alias>CR.71c</alias>
|
||||
<kT> 2.53E-8 </kT> <!-- in MeV -->
|
||||
<order>0</order>
|
||||
<fissionable>false</fissionable>
|
||||
|
||||
<!-- The data itself, like tallies,
|
||||
goes from low energies (groups) to high energies
|
||||
-->
|
||||
<absorption>
|
||||
1.70490000E-03 8.36224000E-03 8.37901000E-02 3.97797000E-01 6.98763000E-01 9.29508000E-01 1.17836000E+00
|
||||
</absorption>
|
||||
|
||||
<!-- for consistency must include nu-scatter -->
|
||||
<!-- will be a matrix of (order+1) x g_in x g_out -->
|
||||
<scatter>
|
||||
1.70563000E-01 4.44012000E-02 9.83670000E-05 1.27786000E-07 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 4.71050000E-01 6.85480000E-04 3.91395000E-10 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 8.01859000E-01 7.20132000E-04 0.00000000E+00 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 5.70752000E-01 1.46015000E-03 0.00000000E+00 0.00000000E+00
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 6.55562000E-05 2.07838000E-01 3.81486000E-03 3.69760000E-09
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 1.02427000E-03 2.02465000E-01 4.75290000E-03
|
||||
0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 0.00000000E+00 3.53043000E-03 6.58597000E-01
|
||||
</scatter>
|
||||
|
||||
<total>
|
||||
2.16767595E-01 4.80097720E-01 8.86369232E-01 9.70009150E-01 9.10481420E-01 1.13775017E+00 1.84048743E+00
|
||||
</total>
|
||||
</xsdata>
|
||||
</library>
|
||||
54
examples/xml/multigroup/c5g7/materials.xml
Normal file
54
examples/xml/multigroup/c5g7/materials.xml
Normal file
|
|
@ -0,0 +1,54 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
<!-- Set default xs set to 71c, which is ENDF-B/VII.0 at 600K -->
|
||||
<default_xs>71c</default_xs>
|
||||
|
||||
<!-- UO2 -->
|
||||
<material id="1">
|
||||
<density units="macro" value="1.0" />
|
||||
<macroscopic name="UO2"/>
|
||||
</material>
|
||||
|
||||
<!-- 4.3% MOX -->
|
||||
<material id="2">
|
||||
<density units="macro" value="1.0" />
|
||||
<macroscopic name="MOX1"/>
|
||||
</material>
|
||||
|
||||
<!-- 7.0 MOX -->
|
||||
<material id="3">
|
||||
<density units="macro" value="1.0" />
|
||||
<macroscopic name="MOX2"/>
|
||||
</material>
|
||||
|
||||
<!-- 8.0% MOX -->
|
||||
<material id="4">
|
||||
<density units="macro" value="1.0" />
|
||||
<macroscopic name="MOX3"/>
|
||||
</material>
|
||||
|
||||
<!-- Fission Chamber -->
|
||||
<material id="5">
|
||||
<density units="macro" value="1.0" />
|
||||
<macroscopic name="FC"/>
|
||||
</material>
|
||||
|
||||
<!-- Guide Tube -->
|
||||
<material id="6">
|
||||
<density units="macro" value="1.0" />
|
||||
<macroscopic name="GT"/>
|
||||
</material>
|
||||
|
||||
<!-- Water -->
|
||||
<material id="7">
|
||||
<density units="macro" value="1.0" />
|
||||
<macroscopic name="LWTR"/>
|
||||
</material>
|
||||
|
||||
<!-- Control Rod -->
|
||||
<material id="8">
|
||||
<density units="macro" value="1.0" />
|
||||
<macroscopic name="CR"/>
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
16
examples/xml/multigroup/c5g7/pin/geometry.xml
Normal file
16
examples/xml/multigroup/c5g7/pin/geometry.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<geometry>
|
||||
|
||||
|
||||
|
||||
<surface coeffs="0. 0. 0.540" id="1" type="z-cylinder" />
|
||||
|
||||
<surface boundary="reflective" coeffs="-0.63" id="20" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs=" 0.63" id="21" type="x-plane" />
|
||||
<surface boundary="reflective" coeffs="-0.63" id="22" type="y-plane" />
|
||||
<surface boundary="reflective" coeffs=" 0.63" id="23" type="y-plane" />
|
||||
|
||||
|
||||
<cell id="1" material="1" region=" -1" />
|
||||
<cell id="2" material="7" region="1 20 -21 22 -23" />
|
||||
|
||||
</geometry>
|
||||
1
examples/xml/multigroup/c5g7/pin/materials.xml
Symbolic link
1
examples/xml/multigroup/c5g7/pin/materials.xml
Symbolic link
|
|
@ -0,0 +1 @@
|
|||
/home/nelsonag/cases/c5g7/materials.xml
|
||||
28
examples/xml/multigroup/c5g7/pin/plots.xml
Normal file
28
examples/xml/multigroup/c5g7/pin/plots.xml
Normal file
|
|
@ -0,0 +1,28 @@
|
|||
<?xml version="1.0"?>
|
||||
<plots>
|
||||
|
||||
<plot>
|
||||
<id>1</id>
|
||||
<filename>mat</filename>
|
||||
<color>material</color>
|
||||
<origin>0 0 0</origin>
|
||||
<width>1.26 1.26</width>
|
||||
<type>slice</type>
|
||||
<pixels>1000 1000 </pixels>
|
||||
<col_spec id="1" rgb="255 0 0" />
|
||||
<col_spec id="2" rgb="0 0 0" />
|
||||
<col_spec id="3" rgb="0 255 0" />
|
||||
<col_spec id="4" rgb="0 0 255" />
|
||||
</plot>
|
||||
|
||||
<plot>
|
||||
<id>2</id>
|
||||
<filename>cell</filename>
|
||||
<color>cell</color>
|
||||
<origin>0 0 0</origin>
|
||||
<width>1.26 1.26</width>
|
||||
<type>slice</type>
|
||||
<pixels>1000 1000 </pixels>
|
||||
</plot>
|
||||
|
||||
</plots>
|
||||
46
examples/xml/multigroup/c5g7/pin/settings.xml
Normal file
46
examples/xml/multigroup/c5g7/pin/settings.xml
Normal file
|
|
@ -0,0 +1,46 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<energy_mode>multi-group</energy_mode>
|
||||
|
||||
<!--
|
||||
Define how many particles to run and for how many batches
|
||||
in an eigenvalue calculation mode
|
||||
-->
|
||||
<eigenvalue>
|
||||
<batches>2000</batches>
|
||||
<inactive>500</inactive>
|
||||
<particles>1000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!--
|
||||
Start with uniformally distributed neutron source
|
||||
with the default energy spectrum of a Maxwellian
|
||||
and isotropic distribution.
|
||||
-->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>
|
||||
-0.63 -0.63 -1E50
|
||||
0.63 0.63 1E50
|
||||
</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
<!-- Establish statepoints to aid in examining convergence -->
|
||||
<state_point>
|
||||
<interval>2000</interval>
|
||||
<source_write>true</source_write>
|
||||
</state_point>
|
||||
|
||||
<output>
|
||||
<cross_sections>true</cross_sections>
|
||||
<summary>true</summary>
|
||||
<tallies>true</tallies>
|
||||
</output>
|
||||
|
||||
<survival_biasing>false</survival_biasing>
|
||||
|
||||
<cross_sections>../data.xml</cross_sections>
|
||||
|
||||
</settings>
|
||||
16
examples/xml/multigroup/c5g7/pin/tallies.xml
Normal file
16
examples/xml/multigroup/c5g7/pin/tallies.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="cell" bins="1 2" />
|
||||
<filter type="energy" />
|
||||
<scores>flux</scores>
|
||||
</tally>
|
||||
|
||||
<tally id="2">
|
||||
<filter type="energy" />
|
||||
<filter type="energyout" />
|
||||
<scores>scatter</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
|
|
@ -261,8 +261,8 @@ contains
|
|||
call fatal_error("Unrecognized tabular_legendre/enable: " // temp_str)
|
||||
end if
|
||||
else
|
||||
enable_leg_mu = .false.
|
||||
this % legendre_mu_points = 1
|
||||
enable_leg_mu = .true.
|
||||
this % legendre_mu_points = 33
|
||||
end if
|
||||
if (enable_leg_mu .and. &
|
||||
check_for_node(node_legendre_mu, "num_points")) then
|
||||
|
|
|
|||
|
|
@ -88,7 +88,6 @@ contains
|
|||
call scatter(p)
|
||||
|
||||
! Play russian roulette if survival biasing is turned on
|
||||
|
||||
if (survival_biasing) then
|
||||
call russian_roulette(p)
|
||||
if (.not. p % alive) return
|
||||
|
|
@ -143,15 +142,14 @@ contains
|
|||
type(Particle), intent(inout) :: p
|
||||
|
||||
call sample_scatter(macro_xs(p % material) % obj, &
|
||||
p % coord(p % n_coord) % uvw, p % last_g, p % g, &
|
||||
p % coord(1) % uvw, p % last_g, p % g, &
|
||||
p % mu, p % wgt)
|
||||
|
||||
! Update energy value for downstream compatability (in tallying)
|
||||
p % E = energy_bin_avg(p % g)
|
||||
|
||||
! Convert change in angle (mu) to new direction
|
||||
p % coord(p % n_coord) % uvw = rotate_angle(p % coord(p % n_coord) % uvw, &
|
||||
p % mu)
|
||||
p % coord(1) % uvw = rotate_angle(p % coord(1) % uvw, p % mu)
|
||||
|
||||
! Set event component
|
||||
p % event = EVENT_SCATTER
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue