Merge branch 'main' of gitlab:aparler/openmc-designs

This commit is contained in:
Adam Parler 2023-10-26 00:36:48 -07:00
commit 30e319444b
111 changed files with 26811 additions and 0 deletions

22
.gitignore vendored Normal file
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# VS Code
.vscode
# Compiled python modules
*.pyc
# Python egg metadata
validation.egg-info
# emacs and vim backups
*~
*.swp
# macOS
*.DS_Store
# tex outputs
*.tex
# OpenMC Output Files
*.h5
*.ppm

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<?xml version="1.0"?>
<geometry>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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<?xml version="1.0"?>
<materials>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 -->
<material id="1">
<density value="10.5" units="g/cc" />
<nuclide name="U235" xs="71c" wo="0.0185105302348" />
<nuclide name="U238" xs="71c" wo="0.862943290471" />
<nuclide name="O16" xs="71c" wo="0.118546179294" />
</material>
<!-- Helium for gap -->
<material id="2">
<density value="1.00000e-4" units="atom/b-cm" />
<nuclide name="He4" xs="71c" ao="1.0" />
</material>
<!-- Zircaloy 4 -->
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</material>
<!-- Water -->
<material id="4">
<density value="0.73" units="g/cc" />
<nuclide name="H1" xs="71c" ao="2.0" />
<nuclide name="O16" xs="71c" ao="1.0" />
<sab name="c_H_in_H2O" xs="04t" />
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<!-- Guide Tube -->
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</material>
</materials>

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<?xml version="1.0"?>
<plots>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<plot id="1" color="mat" >
<origin>0. 0. 0.</origin>
<width>25.50 25.50 </width>
<pixels>1000 1000 </pixels>
<col_spec id="1" rgb="123 123 231" />
</plot>
</plots>

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<?xml version="1.0"?>
<settings>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<eigenvalue>
<batches>600</batches>
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<particles>10000</particles>
</eigenvalue>
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<space>
<type>box</type>
<parameters>
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10.659 10.659 182.9
</parameters>
</space>
</source>
</settings>

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<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
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<scores>flux</scores>
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</tally>
<tally id="8">
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<scores>delayed-nu-fission</scores>
</tally>
</tallies>

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<?xml version="1.0"?>
<geometry>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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</geometry>

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<?xml version="1.0"?>
<materials>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
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<!-- Fuel composed of U-238 O-16 and U-235 -->
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</material>
<!-- Helium for gap -->
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</material>
<!-- Zircaloy 4 -->
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<nuclide name="Zr96" xs="71c" wo="0.027377" />
</material>
<!-- Water -->
<material id="4">
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<nuclide name="H1" xs="71c" ao="2.0" />
<nuclide name="O16" xs="71c" ao="1.0" />
<sab name="c_H_in_H2O" xs="04t" />
</material>
<!-- Guide Tube -->
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</material>
</materials>

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<?xml version="1.0"?>
<plots>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<plot id="1" color="mat" >
<origin>0. 0. 0.</origin>
<width>25.50 25.50 </width>
<pixels>1000 1000 </pixels>
<col_spec id="1" rgb="123 123 231" />
</plot>
</plots>

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@ -0,0 +1,29 @@
<?xml version="1.0"?>
<settings>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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</eigenvalue>
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<type>box</type>
<parameters>
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</parameters>
</space>
</source>
</settings>

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@ -0,0 +1,77 @@
<?xml version="1.0"?>
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</tally>
</tallies>

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@ -0,0 +1,70 @@
<?xml version="1.0"?>
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====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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</geometry>

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<?xml version="1.0"?>
<materials>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 -->
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View file

@ -0,0 +1,24 @@
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<plots>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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</plot>
</plots>

View file

@ -0,0 +1,29 @@
<?xml version="1.0"?>
<settings>
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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View file

@ -0,0 +1,77 @@
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</tally>
</tallies>

View file

@ -0,0 +1,217 @@
<?xml version="1.0"?>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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</geometry>

View file

@ -0,0 +1,152 @@
<?xml version="1.0"?>
<materials>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
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</material>
<!-- Zircaloy 4 -->
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</materials>

View file

@ -0,0 +1,20 @@
<?xml version="1.0"?>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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</plot>
</plots>

View file

@ -0,0 +1,31 @@
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<settings>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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</settings>

View file

@ -0,0 +1,77 @@
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</tally>
</tallies>

View file

@ -0,0 +1,217 @@
<?xml version="1.0"?>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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View file

@ -0,0 +1,152 @@
<?xml version="1.0"?>
<materials>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
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<!-- Zircaloy 4 -->
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</materials>

View file

@ -0,0 +1,20 @@
<?xml version="1.0"?>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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</plots>

View file

@ -0,0 +1,31 @@
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<settings>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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View file

@ -0,0 +1,77 @@
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</tally>
</tallies>

View file

@ -0,0 +1,217 @@
<?xml version="1.0"?>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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View file

@ -0,0 +1,152 @@
<?xml version="1.0"?>
<materials>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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<nuclide name="O16" xs="72c" wo="13.4529" />
<nuclide name="Dy160" xs="72c" wo="0.1735" />
<nuclide name="Dy161" xs="72c" wo="1.418" />
<nuclide name="Dy162" xs="72c" wo="1.915" />
<nuclide name="Dy163" xs="72c" wo="1.861" />
<nuclide name="Dy164" xs="72c" wo="2.1317" />
</material>
<!-- Zircaloy 4 -->
<material id="2">
<density value="7.48" units="g/cc" />
<nuclide name="O16" xs="71c" wo="0.125" />
<nuclide name="Cr50" xs="71c" wo="0.004345" />
<nuclide name="Cr52" xs="71c" wo="0.083789" />
<nuclide name="Cr53" xs="71c" wo="0.009501" />
<nuclide name="Cr54" xs="71c" wo="0.002365" />
<nuclide name="Sn112" xs="71c" wo="0.014065" />
<nuclide name="Sn114" xs="71c" wo="0.00957" />
<nuclide name="Sn115" xs="71c" wo="0.00493" />
<nuclide name="Sn116" xs="71c" wo="0.21083" />
<nuclide name="Sn117" xs="71c" wo="0.11136" />
<nuclide name="Sn118" xs="71c" wo="0.35119" />
<nuclide name="Sn119" xs="71c" wo="0.124555" />
<nuclide name="Sn120" xs="71c" wo="0.47241" />
<nuclide name="Sn122" xs="71c" wo="0.067135" />
<nuclide name="Sn124" xs="71c" wo="0.083955" />
<nuclide name="Fe54" xs="71c" wo="0.0122745" />
<nuclide name="Fe56" xs="71c" wo="0.1926834" />
<nuclide name="Fe57" xs="71c" wo="0.0044499" />
<nuclide name="Fe58" xs="71c" wo="0.0005922" />
<nuclide name="Zr90" xs="71c" wo="50.48" />
<nuclide name="Zr91" xs="71c" wo="11" />
<nuclide name="Zr92" xs="71c" wo="16.83" />
<nuclide name="Zr94" xs="71c" wo="17.05" />
<nuclide name="Zr96" xs="71c" wo="2.75" />
</material>
<!-- water -->
<material id="3">
<density value="0.71273" units="g/cc" />
<nuclide name="H1" ao="0.6666" />
<nuclide name="O16" ao="0.3334" />
<sab name="c_H_in_H2O" xs="15t" />
</material>
<!-- pressure tubr zr + Nb-->
<material id="4">
<density value="6.57" units="g/cc" />
<nuclide name="Zr90" xs="71c" wo="50.16" />
<nuclide name="Zr91" xs="71c" wo="10.94" />
<nuclide name="Zr92" xs="71c" wo="16.72" />
<nuclide name="Zr94" xs="71c" wo="16.945" />
<nuclide name="Zr96" xs="71c" wo="2.73" />
<nuclide name="Nb93" xs="71c" wo="2.5" />
</material>
<!-- grph -->
<material id="5">
<density value="0.0017" units="g/cc" />
<nuclide name="O16" ao="0.6666" />
<nuclide name="CNat" ao="0.3334" />
<sab name="c_Graphite" xs="11t" />
</material>
<!--Calandria Zirconium alloy grade R60804 -->
<material id="6">
<density value="6.44" units="g/cc" />
<nuclide name="O16" xs="70c" wo="0.125" />
<nuclide name="Cr50" xs="70c" wo="0.004345" />
<nuclide name="Cr52" xs="70c" wo="0.083789" />
<nuclide name="Cr53" xs="70c" wo="0.009501" />
<nuclide name="Cr54" xs="70c" wo="0.002365" />
<nuclide name="Sn112" xs="70c" wo="0.014065" />
<nuclide name="Sn114" xs="70c" wo="0.00957" />
<nuclide name="Sn115" xs="70c" wo="0.00493" />
<nuclide name="Sn116" xs="70c" wo="0.21083" />
<nuclide name="Sn117" xs="70c" wo="0.11136" />
<nuclide name="Sn118" xs="70c" wo="0.35119" />
<nuclide name="Sn119" xs="70c" wo="0.124555" />
<nuclide name="Sn120" xs="70c" wo="0.47241" />
<nuclide name="Sn122" xs="70c" wo="0.067135" />
<nuclide name="Sn124" xs="70c" wo="0.083955" />
<nuclide name="Fe54" xs="70c" wo="0.0122745" />
<nuclide name="Fe56" xs="70c" wo="0.1926834" />
<nuclide name="Fe57" xs="70c" wo="0.004431" />
<nuclide name="Fe58" xs="70c" wo="0.0005922" />
<nuclide name="Zr90" xs="70c" wo="50.16" />
<nuclide name="Zr91" xs="70c" wo="10.94" />
<nuclide name="Zr92" xs="70c" wo="16.72" />
<nuclide name="Zr94" xs="70c" wo="17.94" />
<nuclide name="Zr96" xs="70c" wo="2.73" />
</material>
<!-- Heavy water -->
<material id="7">
<density value="1.07801" units="g/cc" />
<nuclide name="O16" xs="73c" ao="1" />
<nuclide name="H2" xs="80c" ao="1.996" />
<nuclide name="H1" xs="80c" ao="0.004" />
<sab name="c_H_in_H2O" xs="11t" />
<sab name="c_D_in_D2O" xs="11t" />
</material>
</materials>

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<?xml version="1.0"?>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<plots>
<plot basis="xy" id="1" color="mat" >
<origin>0. 0. 0.</origin>
<width>25.0 25.0 </width>
<pixels>1000 1000</pixels>
<!-- <meshlines mesh="1" linewidth="2" color="0 255 0"/> -->
</plot>
</plots>

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<?xml version="1.0"?>
<settings>
<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<!-- Parameters for k-eigenvalue calculation -->
<eigenvalue>
<batches>600</batches>
<inactive>50</inactive>
<particles>10000</particles>
</eigenvalue>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>
-11 -11 -24.765
11 11 24.765
</parameters>
</space>
</source>
</settings>

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<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>93 87</bins>
</filter>
<filter id="2" type="cell">
<bins>93 87</bins>
</filter>
<filter id="3" type="cell">
<bins>93 87</bins>
</filter>
<filter id="4" type="cell">
<bins>93 87</bins>
</filter>
<filter id="5" type="cell">
<bins>93 87</bins>
</filter>
<filter id="6" type="cell">
<bins>93 87</bins>
</filter>
<filter id="7" type="cell">
<bins>93 87</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

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<?xml version="1.0"?>
<depletion_chain>
<nuclide name="I135" decay_modes="1" reactions="1" half_life="2.36520E+04">
<decay type="beta" target="Xe135" branching_ratio="1.0" />
<reaction type="(n,gamma)" Q="0.0" target="Xe136" /> <!-- Not precisely true, but whatever -->
</nuclide>
<nuclide name="Xe135" decay_modes="1" reactions="1" half_life="3.29040E+04">
<decay type=" beta" target="Cs135" branching_ratio="1.0" />
<reaction type="(n,gamma)" Q="0.0" target="Xe136" />
</nuclide>
<nuclide name="Xe136" decay_modes="0" reactions="0" />
<nuclide name="Cs135" decay_modes="0" reactions="0" />
<nuclide name="Gd157" decay_modes="0" reactions="1" >
<reaction type="(n,gamma)" Q="0.0" target="Nothing" />
</nuclide>
<nuclide name="Cs137" half_life="949252600.0" decay_modes="2" decay_energy="179447.6443" reactions="6">
<decay type="beta-" target="Ba137" branching_ratio="0.05300549"/>
<decay type="beta-" target="Ba137_m1" branching_ratio="0.94699451"/>
<source type="discrete" particle="photon">
<parameters>283500.0 4.235177914969822e-15</parameters>
</source>
<source type="discrete" particle="electron">
<parameters>513971.0 892130.0 1175630.0 6.915023250821416e-10 4.235177914969822e-15 3.870076370575872e-11</parameters>
</source>
<reaction type="(n,2n)" Q="-8278100.0" target="Cs136"/>
<reaction type="(n,3n)" Q="-15047200.0" target="Cs135"/>
<reaction type="(n,p)" Q="-3562520.0" target="Xe137"/>
<reaction type="(n,a)" Q="3064210.0" target="I134"/>
<reaction type="(n,gamma)" Q="4281390.0" target="Cs138" branching_ratio="0.9021"/>
<reaction type="(n,gamma)" Q="4281390.0" target="Cs138_m1" branching_ratio="0.0979"/>
</nuclide>
<nuclide name="Ba137" reactions="5">
<reaction type="(n,2n)" Q="-6903090.0" target="Ba136"/>
<reaction type="(n,3n)" Q="-16015200.0" target="Ba135"/>
<reaction type="(n,gamma)" Q="8611390.0" target="Ba138"/>
<reaction type="(n,p)" Q="-390530.0" target="Cs137"/>
<reaction type="(n,a)" Q="6046200.0" target="Xe134"/>
</nuclide>
<nuclide name="Ba137_m1" half_life="153.12" decay_modes="1" decay_energy="661396.64" reactions="0">
<decay type="IT" target="Ba137" branching_ratio="1.0"/>
<source type="discrete" particle="photon">
<parameters>4470.0 31817.0 32194.0 36304.0 36378.0 37255.0 661657.0 4.372683136122041e-05 9.525884763557368e-05 0.00017377297596020668 1.6633087848867745e-05 3.2112650589648466e-05 1.0158463048637348e-05 0.004069614128287558</parameters>
</source>
<source type="discrete" particle="electron">
<parameters>3670.0 26400.0 624216.4 655668.2 660364.2 661404.0 661636.9 0.0003537897992698539 3.7210487357645964e-05 0.00037210482830822686 6.708752100247119e-05 1.4350025269251869e-05 3.08729347663194e-06 4.6173597451093537e-07</parameters>
</source>
</nuclide>
<nuclide name="Gd156" decay_modes="0" reactions="1">
<reaction type="(n,gamma)" Q="0.0" target="Gd157" />
</nuclide>
<nuclide name="U234" decay_modes="0" reactions="1">
<reaction type="fission" Q="191840000."/>
<neutron_fission_yields>
<energies>2.53000e-02</energies>
<fission_yields energy="2.53000e-02">
<products>Gd157 Gd156 I135 Xe135 Xe136 Cs135</products>
<data>1.093250e-04 2.087260e-04 2.780820e-02 6.759540e-03 2.392300e-02 4.356330e-05</data>
</fission_yields>
</neutron_fission_yields>
</nuclide>
<nuclide name="U235" decay_modes="0" reactions="1">
<reaction type="fission" Q="193410000."/>
<neutron_fission_yields>
<energies>2.53000e-02</energies>
<fission_yields energy="2.53000e-02">
<products>Gd157 Gd156 I135 Xe135 Xe136 Cs135</products>
<data>6.142710e-5 1.483250e-04 0.0292737 0.002566345 0.0219242 4.9097e-6</data>
</fission_yields>
</neutron_fission_yields>
</nuclide>
<nuclide name="U238" decay_modes="0" reactions="1">
<reaction type="fission" Q="197790000."/>
<neutron_fission_yields>
<energies>2.53000e-02</energies>
<fission_yields energy="2.53000e-02">
<products>Gd157 Gd156 I135 Xe135 Xe136 Cs135</products>
<data>4.141120e-04 7.605360e-04 0.0135457 0.00026864 0.0024432 3.7100E-07</data>
</fission_yields>
</neutron_fission_yields>
</nuclide>
</depletion_chain>

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MIT License
Copyright (c) 2023 Adam Parler
Permission is hereby granted, free of charge, to any person obtaining a copy
of this software and associated documentation files (the "Software"), to deal
in the Software without restriction, including without limitation the rights
to use, copy, modify, merge, publish, distribute, sublicense, and/or sell
copies of the Software, and to permit persons to whom the Software is
furnished to do so, subject to the following conditions:
The above copyright notice and this permission notice shall be included in all
copies or substantial portions of the Software.
THE SOFTWARE IS PROVIDED "AS IS", WITHOUT WARRANTY OF ANY KIND, EXPRESS OR
IMPLIED, INCLUDING BUT NOT LIMITED TO THE WARRANTIES OF MERCHANTABILITY,
FITNESS FOR A PARTICULAR PURPOSE AND NONINFRINGEMENT. IN NO EVENT SHALL THE
AUTHORS OR COPYRIGHT HOLDERS BE LIABLE FOR ANY CLAIM, DAMAGES OR OTHER
LIABILITY, WHETHER IN AN ACTION OF CONTRACT, TORT OR OTHERWISE, ARISING FROM,
OUT OF OR IN CONNECTION WITH THE SOFTWARE OR THE USE OR OTHER DEALINGS IN THE
SOFTWARE.

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# OpenMCProject
This repository is amalgamation of various simulations I found interesting. They are joined together to make one giant simulation repo.
Files have been updated to run with `v0.13.3` of [OpenMC](https://github.com/openmc-dev/openmc/tree/v0.13.3)

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<?xml version='1.0' encoding='utf-8'?>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<geometry>
<cell fill="5" id="1" region="1 -2 -80 110 -70 100 -120 90" />
<cell id="101" material="void" region="-5" universe="909" />
<cell id="102" material="1" region="5 -6" universe="909" />
<cell id="500" material="void" region="6 -7" universe="909"/>
<cell id="600" material="2" region="7 -8" universe="909" />
<cell id="100" material="3" region="8" universe="909" />
<cell id="111" material="void" region="-5" universe="709" />
<cell id="112" material="5" region="5 -6" universe="709" />
<cell id="510" material="void" region="6 -7" universe="709"/>
<cell id="610" material="2" region="7 -8" universe="709" />
<cell id="110" material="3" region="8" universe="709" />
<cell id="107" material="3" region="-9" universe="808" />
<cell id="108" material="4" region="9 -10" universe="808" />
<cell id="109" material="3" region="10" universe="808" />
<cell id="103" material="3" region="-11" universe="505" />
<cell id="105" material="4" region="11 -12" universe="505" />
<cell id="106" material="3" region="12" universe="505" />
<cell id="601" material="3" universe="900" />
<hex_lattice id="5" n_rings="11">
<pitch>1.275 </pitch>
<outer>900</outer>
<center>0.0 0.0 </center>
<universes> 909
909 909
909 909 909
909 909 909 909
909 909 909 909 909
909 909 909 909 909 909
909 909 909 909 909 909 909
909 909 909 909 909 909 909 909
909 909 709 909 909 909 709 909 909
909 909 909 909 909 909 909 909 909 909
909 909 909 909 909 808 909 909 909 909 909
909 909 909 808 909 909 808 909 909 909
909 909 909 909 909 909 909 909 909 909 909
909 909 909 909 709 909 909 909 909 909
909 909 909 909 909 909 909 909 909 909 909
909 909 808 909 909 808 709 808 909 909
909 909 909 909 808 909 909 909 909 909 909
909 909 909 909 909 909 909 909 909 909
909 909 909 709 909 909 909 909 909 909 909
909 909 909 909 909 909 808 909 909 909
909 709 808 909 909 505 909 909 808 709 909
909 909 909 808 909 909 909 909 909 909
909 909 909 909 909 909 909 709 909 909 909
909 909 909 909 909 909 909 909 909 909
909 909 909 909 909 909 808 909 909 909 909
909 909 808 709 808 909 909 808 909 909
909 909 909 909 909 909 909 909 909 909 909
909 909 909 909 909 709 909 909 909 909
909 909 909 909 909 909 909 909 909 909 909
909 909 909 808 909 909 808 909 909 909
909 909 909 909 909 808 909 909 909 909 909
909 909 909 909 909 909 909 909 909 909
909 909 709 909 909 909 709 909 909
909 909 909 909 909 909 909 909
909 909 909 909 909 909 909
909 909 909 909 909 909
909 909 909 909 909
909 909 909 909
909 909 909
909 909
909
</universes>
</hex_lattice>
<surface id="1" type="z-plane" coeffs="-176.5" boundary="reflective" />
<surface id="2" type="z-plane" coeffs="176.5" boundary="reflective" />
<surface id="70" type="plane" coeffs="1 1.73205 0 23.6" boundary="reflective"/>
<surface id="80" type="x-plane" coeffs="11.8" boundary="reflective" />
<surface id="90" type="plane" coeffs="-1 1.73205 0 -23.6" boundary="reflective" />
<surface id="100" type="plane" coeffs="1 1.73205 0 -23.6 " boundary="reflective" />
<surface id="110" type="x-plane" coeffs="-11.8 " boundary="reflective" />
<surface id="120" type="plane" coeffs="-1 1.73205 0 23.6" boundary="reflective" />
<surface id="5" type="z-cylinder" coeffs="0. 0. 0.075" />
<surface id="6" type="z-cylinder" coeffs="0. 0. 0.3785" />
<surface id="7" type="z-cylinder" coeffs="0. 0. 0.3865" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 0.455" />
<surface id="9" type="z-cylinder" coeffs="0. 0. 0.545" />
<surface id="10" type="z-cylinder" coeffs="0. 0. 0.628" />
<surface id="11" type="z-cylinder" coeffs="0. 0. 0.55" />
<surface id="12" type="z-cylinder" coeffs="0. 0. 0.63" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 2.1% -->
<material id="1">
<density value="10.55" units="g/cc" />
<nuclide name="U235" xs="80c" wo="0.0185105302348" />
<nuclide name="U238" xs="80c" wo="0.862943290471" />
<nuclide name="O16" xs="80c" wo="0.118546179294" />
</material>
<!-- 3.6% UO2 + 5% Gd2O3 -->
<material id="5">
<density value="10.547" units="g/cc" />
<nuclide name="U235" xs="80c" wo="0.0292792" />
<nuclide name="U238" xs="80c" wo="0.7940422" />
<nuclide name="O16" xs="80c" wo="0.1194922" />
<nuclide name="Gd157" xs="80c" wo="0.0571954 " />
</material>
<!-- Cladding material alloy Э110 -->
<material id="2">
<density value="6.4516" units="g/cc" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Hf174" xs="80c" wo="0.00000048" />
<nuclide name="Hf176" xs="80c" wo="0.00001578" />
<nuclide name="Hf177" xs="80c" wo="0.0000558" />
<nuclide name="Hf178" xs="80c" wo="0.00008184" />
<nuclide name="Hf179" xs="80c" wo="0.00004086" />
<nuclide name="Hf180" xs="80c" wo="0.00010524" />
<nuclide name="Zr90" xs="80c" wo="0.50920065" />
<nuclide name="Zr91" xs="80c" wo="0.11104434" />
<nuclide name="Zr92" xs="80c" wo="0.16973355" />
<nuclide name="Zr94" xs="80c" wo="0.17200986" />
<nuclide name="Zr96" xs="80c" wo="0.0277116" />
</material>
<!-- Water -->
<material id="3">
<density value="0.716" units="g/cc" />
<nuclide name="H1" xs="80c" wo="0.06312" />
<nuclide name="O16" xs="80c" wo="0.13539" />
<nuclide name="B11" xs="80c" wo="0.80149" />
</material>
<!-- Guide Tube alloy Э635 -->
<material id="4">
<density value="6.55" units="g/cc" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Sn112" xs="80c" wo="0.0001261" />
<nuclide name="Sn114" xs="80c" wo="0.0000858" />
<nuclide name="Sn115" xs="80c" wo="0.0000442" />
<nuclide name="Sn116" xs="80c" wo="0.0018902" />
<nuclide name="Sn117" xs="80c" wo="0.0009984" />
<nuclide name="Sn118" xs="80c" wo="0.0031486" />
<nuclide name="Sn119" xs="80c" wo="0.0011167" />
<nuclide name="Sn120" xs="80c" wo="0.0042354" />
<nuclide name="Sn122" xs="80c" wo="0.0006019" />
<nuclide name="Sn124" xs="80c" wo="0.0007527" />
<nuclide name="Fe54" xs="80c" wo="0.00017535" />
<nuclide name="Fe56" xs="80c" wo="0.00275262" />
<nuclide name="Fe57" xs="80c" wo="0.00006357" />
<nuclide name="Fe58" xs="80c" wo="0.00000846" />
<nuclide name="Zr90" xs="80c" wo="0.50662815" />
<nuclide name="Zr91" xs="80c" wo="0.11048334" />
<nuclide name="Zr92" xs="80c" wo="0.16887605" />
<nuclide name="Zr94" xs="80c" wo="0.17114086" />
<nuclide name="Zr96" xs="80c" wo="0.0275716" />
</material>
</materials>

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<?xml version="1.0"?>
<plots>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<plot basis="xy" id="1" color="mat" >
<origin>0. 0. 0.</origin>
<width>30.50 30.50 </width>
<pixels>1000 1000 </pixels>
<col_spec id="5" rgb="123 123 231" />
</plot>
<plot basis="yz" id="2" color="mat" >
<origin>0. 0. 0.</origin>
<width>50.50 50.50 </width>
<pixels>1000 1000 </pixels>
</plot>
</plots>

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@ -0,0 +1,28 @@
<?xml version='1.0' encoding='utf-8'?>
<settings>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<eigenvalue>
<batches>600</batches>
<inactive>50</inactive>
<particles>10000</particles>
</eigenvalue>
<source>
<space>
<type>point</type>
<parameters>
0.0 0.0 0.0
</parameters>
</space>
</source>
</settings>

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<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>1</bins>
</filter>
<filter id="3" type="cell">
<bins>1</bins>
</filter>
<filter id="4" type="cell">
<bins>1</bins>
</filter>
<filter id="5" type="cell">
<bins>1</bins>
</filter>
<filter id="6" type="cell">
<bins>1</bins>
</filter>
<filter id="7" type="cell">
<bins>1</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

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<?xml version='1.0' encoding='utf-8'?>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<geometry>
<cell fill="5" id="1" region="1 -2 -80 110 -70 100 -120 90" />
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<cell id="601" material="3" universe="900" />
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909 909 909 909 909 909 909 909 909 909
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909 909 909 909 909 909 909 709 909 909 909
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909 909 909 909 909 909 909 909 909 909 909
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909 909 909 909 909 808 909 909 909 909 909
909 909 909 909 909 909 909 909 909 909
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909 909 909 909 909 909 909 909
909 909 909 909 909 909 909
909 909 909 909 909 909
909 909 909 909 909
909 909 909 909
909 909 909
909 909
909
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<surface id="2" type="z-plane" coeffs="176.5" boundary="reflective" />
<surface id="70" type="plane" coeffs="1 1.73205 0 23.6" boundary="reflective"/>
<surface id="80" type="x-plane" coeffs="11.8" boundary="reflective" />
<surface id="90" type="plane" coeffs="-1 1.73205 0 -23.6" boundary="reflective" />
<surface id="100" type="plane" coeffs="1 1.73205 0 -23.6 " boundary="reflective" />
<surface id="110" type="x-plane" coeffs="-11.8 " boundary="reflective" />
<surface id="120" type="plane" coeffs="-1 1.73205 0 23.6" boundary="reflective" />
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<surface id="6" type="z-cylinder" coeffs="0. 0. 0.3785" />
<surface id="7" type="z-cylinder" coeffs="0. 0. 0.3865" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 0.455" />
<surface id="9" type="z-cylinder" coeffs="0. 0. 0.545" />
<surface id="10" type="z-cylinder" coeffs="0. 0. 0.628" />
<surface id="11" type="z-cylinder" coeffs="0. 0. 0.55" />
<surface id="12" type="z-cylinder" coeffs="0. 0. 0.63" />
</geometry>

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@ -0,0 +1,85 @@
<?xml version='1.0' encoding='utf-8'?>
<materials>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 2.6% -->
<material id="1">
<density value="10.55" units="g/cc" />
<nuclide name="U235" xs="80c" wo="0.0229176280555" />
<nuclide name="U238" xs="80c" wo="0.858529604849" />
<nuclide name="O16" xs="80c" wo="0.118552767096" />
</material>
<!-- 3.6% UO2 + 5% Gd2O3 -->
<material id="5">
<density value="10.547" units="g/cc" />
<nuclide name="U235" xs="80c" wo="0.0292792" />
<nuclide name="U238" xs="80c" wo="0.7940422" />
<nuclide name="O16" xs="80c" wo="0.1194922" />
<nuclide name="Gd157" xs="80c" wo="0.0571954 " />
</material>
<!-- Cladding material alloy Э110 -->
<material id="2">
<density value="6.4516" units="g/cc" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Hf174" xs="80c" wo="0.00000048" />
<nuclide name="Hf176" xs="80c" wo="0.00001578" />
<nuclide name="Hf177" xs="80c" wo="0.0000558" />
<nuclide name="Hf178" xs="80c" wo="0.00008184" />
<nuclide name="Hf179" xs="80c" wo="0.00004086" />
<nuclide name="Hf180" xs="80c" wo="0.00010524" />
<nuclide name="Zr90" xs="80c" wo="0.50920065" />
<nuclide name="Zr91" xs="80c" wo="0.11104434" />
<nuclide name="Zr92" xs="80c" wo="0.16973355" />
<nuclide name="Zr94" xs="80c" wo="0.17200986" />
<nuclide name="Zr96" xs="80c" wo="0.0277116" />
</material>
<!-- Water -->
<material id="3">
<density value="0.716" units="g/cc" />
<nuclide name="H1" xs="80c" wo="0.06312" />
<nuclide name="O16" xs="80c" wo="0.13539" />
<nuclide name="B11" xs="80c" wo="0.80149" />
</material>
<!-- Guide Tube alloy Э635 -->
<material id="4">
<density value="6.55" units="g/cc" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Sn112" xs="80c" wo="0.0001261" />
<nuclide name="Sn114" xs="80c" wo="0.0000858" />
<nuclide name="Sn115" xs="80c" wo="0.0000442" />
<nuclide name="Sn116" xs="80c" wo="0.0018902" />
<nuclide name="Sn117" xs="80c" wo="0.0009984" />
<nuclide name="Sn118" xs="80c" wo="0.0031486" />
<nuclide name="Sn119" xs="80c" wo="0.0011167" />
<nuclide name="Sn120" xs="80c" wo="0.0042354" />
<nuclide name="Sn122" xs="80c" wo="0.0006019" />
<nuclide name="Sn124" xs="80c" wo="0.0007527" />
<nuclide name="Fe54" xs="80c" wo="0.00017535" />
<nuclide name="Fe56" xs="80c" wo="0.00275262" />
<nuclide name="Fe57" xs="80c" wo="0.00006357" />
<nuclide name="Fe58" xs="80c" wo="0.00000846" />
<nuclide name="Zr90" xs="80c" wo="0.50662815" />
<nuclide name="Zr91" xs="80c" wo="0.11048334" />
<nuclide name="Zr92" xs="80c" wo="0.16887605" />
<nuclide name="Zr94" xs="80c" wo="0.17114086" />
<nuclide name="Zr96" xs="80c" wo="0.0275716" />
</material>
</materials>

View file

@ -0,0 +1,28 @@
<?xml version="1.0"?>
<plots>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<plot basis="xy" id="1" color="mat" >
<origin>0. 0. 0.</origin>
<width>30.50 30.50 </width>
<pixels>1000 1000 </pixels>
<col_spec id="5" rgb="123 123 231" />
</plot>
<plot basis="yz" id="2" color="mat" >
<origin>0. 0. 0.</origin>
<width>50.50 50.50 </width>
<pixels>1000 1000 </pixels>
</plot>
</plots>

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@ -0,0 +1,28 @@
<?xml version='1.0' encoding='utf-8'?>
<settings>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<eigenvalue>
<batches>600</batches>
<inactive>50</inactive>
<particles>10000</particles>
</eigenvalue>
<source>
<space>
<type>point</type>
<parameters>
0.0 0.0 0.0
</parameters>
</space>
</source>
</settings>

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@ -0,0 +1,77 @@
<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>1</bins>
</filter>
<filter id="3" type="cell">
<bins>1</bins>
</filter>
<filter id="4" type="cell">
<bins>1</bins>
</filter>
<filter id="5" type="cell">
<bins>1</bins>
</filter>
<filter id="6" type="cell">
<bins>1</bins>
</filter>
<filter id="7" type="cell">
<bins>1</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

View file

@ -0,0 +1,111 @@
<?xml version='1.0' encoding='utf-8'?>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<geometry>
<cell fill="5" id="1" region="1 -2 -80 110 -70 100 -120 90" />
<cell id="101" material="void" region="-5" universe="909" />
<cell id="102" material="1" region="5 -6" universe="909" />
<cell id="500" material="void" region="6 -7" universe="909"/>
<cell id="600" material="2" region="7 -8" universe="909" />
<cell id="100" material="3" region="8" universe="909" />
<cell id="111" material="void" region="-5" universe="709" />
<cell id="112" material="5" region="5 -6" universe="709" />
<cell id="510" material="void" region="6 -7" universe="709"/>
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<cell id="110" material="3" region="8" universe="709" />
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<cell id="109" material="3" region="10" universe="808" />
<cell id="103" material="3" region="-11" universe="505" />
<cell id="105" material="4" region="11 -12" universe="505" />
<cell id="106" material="3" region="12" universe="505" />
<cell id="601" material="3" universe="900" />
<hex_lattice id="5" n_rings="11">
<pitch>1.275 </pitch>
<outer>900</outer>
<center>0.0 0.0 </center>
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909 909 909 909 909 909 909 709 909 909 909
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909 909 909 909 909 909 808 909 909 909 909
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909 909 909 909 909 909 909 909 909 909 909
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909 909 909 909 909 808 909 909 909 909 909
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909 909 909 909 909 909 909 909
909 909 909 909 909 909 909
909 909 909 909 909 909
909 909 909 909 909
909 909 909 909
909 909 909
909 909
909
</universes>
</hex_lattice>
<surface id="1" type="z-plane" coeffs="-176.5" boundary="reflective" />
<surface id="2" type="z-plane" coeffs="176.5" boundary="reflective" />
<surface id="70" type="plane" coeffs="1 1.73205 0 23.6" boundary="reflective"/>
<surface id="80" type="x-plane" coeffs="11.8" boundary="reflective" />
<surface id="90" type="plane" coeffs="-1 1.73205 0 -23.6" boundary="reflective" />
<surface id="100" type="plane" coeffs="1 1.73205 0 -23.6 " boundary="reflective" />
<surface id="110" type="x-plane" coeffs="-11.8 " boundary="reflective" />
<surface id="120" type="plane" coeffs="-1 1.73205 0 23.6" boundary="reflective" />
<surface id="5" type="z-cylinder" coeffs="0. 0. 0.075" />
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<surface id="7" type="z-cylinder" coeffs="0. 0. 0.3865" />
<surface id="8" type="z-cylinder" coeffs="0. 0. 0.455" />
<surface id="9" type="z-cylinder" coeffs="0. 0. 0.545" />
<surface id="10" type="z-cylinder" coeffs="0. 0. 0.628" />
<surface id="11" type="z-cylinder" coeffs="0. 0. 0.55" />
<surface id="12" type="z-cylinder" coeffs="0. 0. 0.63" />
</geometry>

View file

@ -0,0 +1,85 @@
<?xml version='1.0' encoding='utf-8'?>
<materials>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 3.7% -->
<material id="1">
<density value="10.55" units="g/cc" />
<nuclide name="U235" xs="80c" wo="0.03221694" />
<nuclide name="U238" xs="80c" wo="0.84921578" />
<nuclide name="O16" xs="80c" wo="0.11856726" />
</material>
<!-- 3.6% UO2 + 5% Gd2O3 -->
<material id="5">
<density value="10.547" units="g/cc" />
<nuclide name="U235" xs="80c" wo="0.0292792" />
<nuclide name="U238" xs="80c" wo="0.7940422" />
<nuclide name="O16" xs="80c" wo="0.1194922" />
<nuclide name="Gd157" xs="80c" wo="0.0571954 " />
</material>
<!-- Cladding material alloy Э110 -->
<material id="2">
<density value="6.4516" units="g/cc" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Hf174" xs="80c" wo="0.00000048" />
<nuclide name="Hf176" xs="80c" wo="0.00001578" />
<nuclide name="Hf177" xs="80c" wo="0.0000558" />
<nuclide name="Hf178" xs="80c" wo="0.00008184" />
<nuclide name="Hf179" xs="80c" wo="0.00004086" />
<nuclide name="Hf180" xs="80c" wo="0.00010524" />
<nuclide name="Zr90" xs="80c" wo="0.50920065" />
<nuclide name="Zr91" xs="80c" wo="0.11104434" />
<nuclide name="Zr92" xs="80c" wo="0.16973355" />
<nuclide name="Zr94" xs="80c" wo="0.17200986" />
<nuclide name="Zr96" xs="80c" wo="0.0277116" />
</material>
<!-- Water -->
<material id="3">
<density value="0.716" units="g/cc" />
<nuclide name="H1" xs="80c" wo="0.06312" />
<nuclide name="O16" xs="80c" wo="0.13539" />
<nuclide name="B11" xs="80c" wo="0.80149" />
</material>
<!-- Guide Tube alloy Э635 -->
<material id="4">
<density value="6.55" units="g/cc" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Sn112" xs="80c" wo="0.0001261" />
<nuclide name="Sn114" xs="80c" wo="0.0000858" />
<nuclide name="Sn115" xs="80c" wo="0.0000442" />
<nuclide name="Sn116" xs="80c" wo="0.0018902" />
<nuclide name="Sn117" xs="80c" wo="0.0009984" />
<nuclide name="Sn118" xs="80c" wo="0.0031486" />
<nuclide name="Sn119" xs="80c" wo="0.0011167" />
<nuclide name="Sn120" xs="80c" wo="0.0042354" />
<nuclide name="Sn122" xs="80c" wo="0.0006019" />
<nuclide name="Sn124" xs="80c" wo="0.0007527" />
<nuclide name="Fe54" xs="80c" wo="0.00017535" />
<nuclide name="Fe56" xs="80c" wo="0.00275262" />
<nuclide name="Fe57" xs="80c" wo="0.00006357" />
<nuclide name="Fe58" xs="80c" wo="0.00000846" />
<nuclide name="Zr90" xs="80c" wo="0.50662815" />
<nuclide name="Zr91" xs="80c" wo="0.11048334" />
<nuclide name="Zr92" xs="80c" wo="0.16887605" />
<nuclide name="Zr94" xs="80c" wo="0.17114086" />
<nuclide name="Zr96" xs="80c" wo="0.0275716" />
</material>
</materials>

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<?xml version="1.0"?>
<plots>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<plot basis="xy" id="1" color="mat" >
<origin>0. 0. 0.</origin>
<width>30.50 30.50 </width>
<pixels>1000 1000 </pixels>
<col_spec id="5" rgb="123 123 231" />
</plot>
<plot basis="yz" id="2" color="mat" >
<origin>0. 0. 0.</origin>
<width>50.50 50.50 </width>
<pixels>1000 1000 </pixels>
</plot>
</plots>

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<?xml version='1.0' encoding='utf-8'?>
<settings>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<eigenvalue>
<batches>600</batches>
<inactive>50</inactive>
<particles>10000</particles>
</eigenvalue>
<source>
<space>
<type>point</type>
<parameters>
0.0 0.0 0.0
</parameters>
</space>
</source>
</settings>

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<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>1</bins>
</filter>
<filter id="3" type="cell">
<bins>1</bins>
</filter>
<filter id="4" type="cell">
<bins>1</bins>
</filter>
<filter id="5" type="cell">
<bins>1</bins>
</filter>
<filter id="6" type="cell">
<bins>1</bins>
</filter>
<filter id="7" type="cell">
<bins>1</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

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mc-performance/mcnp/input Normal file
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Monte Carlo Performance Benchmark, version 1.2, July 2011
c
c Core Lattice (Lower Half)
c
100 0 -6 34 -35 fill=10 imp:n=1
1 0 25 -26 27 -28 imp:n=1 lat=1 u=10 fill=-10:10 -10:10 0:0
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5
5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5
5 5 5 5 5 6 6 6 6 6 6 6 6 6 6 6 5 5 5 5 5
5 5 5 5 5 5 5 6 6 6 6 6 6 6 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5
c
c Core Lattice (Lower Half)
c
c
200 0 -6 35 -36 fill=20 imp:n=1
2 0 25 -26 27 -28 imp:n=1 lat=1 u=20 fill=-10:10 -10:10 0:0
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7
7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7
7 7 7 7 7 8 8 8 8 8 8 8 8 8 8 8 7 7 7 7 7
7 7 7 7 7 7 7 8 8 8 8 8 8 8 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7 7
c
c All other geometry on base universe
c
3 8 -7.184 -7 31 -32 imp:n=1 $ lower core plate region
4 9 -2.53 -5 32 -33 imp:n=1 $ bottom nozzle region
5 12 -1.762 -5 33 -34 imp:n=1 $ bottom FA region
6 11 -3.044 -5 36 -37 imp:n=1 $ top FA region
7 10 -1.746 -5 37 -38 imp:n=1 $ top nozzle region
8 7 -4.28 -7 38 -39 imp:n=1 $ upper plate region
9 3 0.07416 6 -7 32 -38 imp:n=1 $ downcomer
10 5 -7.9 7 -8 31 -39 imp:n=1 $ reactor pressure vessel
11 6 -4.32 5 -6 32 -34 imp:n=1 $ bottom of radial reflector
12 7 -4.28 5 -6 36 -38 imp:n=1 $ top of radial reflector
c
c Fuel pin, cladding, cold water
c
21 1 -10.062 -1 u=1 imp:n=1
22 2 -5.77 1 -2 u=1 imp:n=1
23 3 0.07416 2 u=1 imp:n=1
c
c Instrumentation guide tube w/ cold water
c
24 3 0.07416 -3 u=2 imp:n=1
25 2 -5.77 3 -4 u=2 imp:n=1
26 3 0.07416 4 u=2 imp:n=1
c
c Fuel pin, cladding, hot water
c
27 1 -10.062 -1 u=3 imp:n=1
28 2 -5.77 1 -2 u=3 imp:n=1
29 4 0.06614 2 u=3 imp:n=1
c
c Instrumentation guide tube w/ hot water
c
30 4 0.06614 -3 u=4 imp:n=1
31 2 -5.77 3 -4 u=4 imp:n=1
32 4 0.06614 4 u=4 imp:n=1
c
c Water Assembly (Lower half)
c
50 3 0.07416 25 -26 27 -28 u=5 imp:n=1
c
c Fuel Assembly Lattice (Lower half)
c
60 0 21 -22 23 -24 imp:n=1 lat=1 u=6 fill=-8:8 -8:8 0:0
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 2 1 1 2 1 1 2 1 1 2 1 1 2 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 2 1 1 1 1 1 1 1 1 1 2 1 1 1
1 1 1 1 1 2 1 1 2 1 1 2 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
c
c Water Assembly (Upper half)
c
70 4 0.06614 25 -26 27 -28 u=7 imp:n=1
c
c Fuel Assembly Lattice (Upper half)
c
80 0 21 -22 23 -24 imp:n=1 lat=1 u=8 fill=-8:8 -8:8 0:0
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 4 3 3 4 3 3 4 3 3 4 3 3 4 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 4 3 3 3 3 3 3 3 3 3 4 3 3 3
3 3 3 3 3 4 3 3 4 3 3 4 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
99 0 8:-31:39 imp:n=0
c
c Surfaces
c
1 cz 0.41
2 cz 0.475
3 cz 0.56
4 cz 0.62
5 cz 187.6
6 cz 209.0
7 cz 229.0
8 cz 249.0
21 px -0.63
22 px 0.63
23 py -0.63
24 py 0.63
25 px -10.71
26 px 10.71
27 py -10.71
28 py 10.71
31 pz -229.0
32 pz -199.0
33 pz -193.0
34 pz -183.0
35 pz 0.0
36 pz 183.0
37 pz 203.0
38 pz 215.0
39 pz 223.0
c
c Materials
c
m1 92234.70c 4.9476e-6
92235.70c 4.8218e-4
92236.70c 9.0402e-5
92238.70c 2.1504e-2
93237.70c 7.3733e-6
94238.70c 1.5148e-6
94239.70c 1.3955e-4
94240.70c 3.4405e-5
94241.70c 2.1439e-5
94242.70c 3.7422e-6
95241.70c 4.5041e-7
95242.70c 9.2301e-9
95243.70c 4.7878e-7
96242.70c 1.0485e-7
96243.70c 1.4268e-9
96244.70c 8.8756e-8
96245.70c 3.5285e-9
42095.70c 2.6497e-5
43099.70c 3.2772e-5
44101.70c 3.0742e-5
44103.70c 2.3505e-6
47109.70c 2.0009e-6
54135.70c 1.0801e-8
55133.70c 3.4612e-5
60143.70c 2.6078e-5
60145.70c 1.9898e-5
62147.70c 1.6128e-6
62149.70c 1.1627e-7
62150.70c 7.1727e-6
62151.70c 5.4947e-7
62152.70c 3.0221e-6
63153.70c 2.6209e-6
64155.70c 1.5369e-9
8016.70c 4.5737e-2
m2 40090.70c 0.5145
40091.70c 0.1122
40092.70c 0.1715
40094.70c 0.1738
40096.70c 0.0280
m3 1001.70c 2.0
8016.70c 1.0
5010.70c 6.490e-4
5011.70c 2.689e-3
mt3 lwtr.10t
m4 1001.70c 2.0
8016.70c 1.0
5010.70c 6.490e-4
5011.70c 2.689e-3
mt4 lwtr.10t
m5 26054.70c -0.05437098
26056.70c -0.88500663
26057.70c -0.0208008
26058.70c -0.00282159
28058.70c -0.0067198
28060.70c -0.0026776
28061.70c -0.0001183
28062.70c -0.0003835
28064.70c -0.0001008
25055.70c -0.01
42092.70c -0.000849
42094.70c -0.0005418
42095.70c -0.0009438
42096.70c -0.0010002
42097.70c -0.0005796
42098.70c -0.0014814
42100.70c -0.0006042
14028.70c -0.00367464
14029.70c -0.00019336
14030.70c -0.000132
24050.70c -0.00010435
24052.70c -0.002092475
24053.70c -0.00024185
24054.70c -6.1325e-05
6000.70c -0.0025
29063.70c -0.0013696
29065.70c -0.0006304
m6 1001.70c -0.0095661
8016.70c -0.0759107
5010.70c -3.08409e-5
5011.70c -1.40499e-4
26054.70c -0.035620772088
26056.70c -0.579805982228
26057.70c -0.01362750048
26058.70c -0.001848545204
28058.70c -0.055298376566
28060.70c -0.022034425592
28061.70c -0.000973510811
28062.70c -0.003155886695
28064.70c -0.000829500336
25055.70c -0.0182870
14028.70c -0.00839976771
14029.70c -0.00044199679
14030.70c -0.0003017355
24050.70c -0.007251360806
24052.70c -0.145407678031
24053.70c -0.016806340306
24054.70c -0.004261520857
mt6 lwtr.10t
m7 1001.70c -0.0086117
8016.70c -0.0683369
5010.70c -2.77638e-5
5011.70c -1.26481e-4
26054.70c -0.035953677186
26056.70c -0.585224740891
26057.70c -0.01375486056
26058.70c -0.001865821363
28058.70c -0.055815129186
28060.70c -0.022240333032
28061.70c -0.000982608081
28062.70c -0.003185377845
28064.70c -0.000837251856
25055.70c -0.0184579
14028.70c -0.00847831314
14029.70c -0.00044612986
14030.70c -0.000304557
24050.70c -0.00731912987
24052.70c -0.146766614995
24053.70c -0.01696340737
24054.70c -0.004301347765
mt7 lwtr.10t
m8 1001.70c -0.0011505
8016.70c -0.0091296
5010.70c -3.70915e-6
5011.70c -1.68974e-5
26054.70c -0.03855611055
26056.70c -0.627585036425
26057.70c -0.014750478
26058.70c -0.002000875025
28058.70c -0.059855207342
28060.70c -0.023850159704
28061.70c -0.001053732407
28062.70c -0.003415945715
28064.70c -0.000897854832
25055.70c -0.0197940
14028.70c -0.00909197802
14029.70c -0.00047842098
14030.70c -0.000326601
24050.70c -0.007848910646
24052.70c -0.157390026871
24053.70c -0.018191270146
24054.70c -0.004612692337
mt8 lwtr.10t
m9 1001.70c -0.0245014
8016.70c -0.1944274
5010.70c -7.89917e-5
5011.70c -3.59854e-4
26054.70c -0.030411411144
26056.70c -0.495012237964
26057.70c -0.01163454624
26058.70c -0.001578204652
28058.70c -0.047211231662
28060.70c -0.018811987544
28061.70c -0.000831139127
28062.70c -0.002694352115
28064.70c -0.000708189552
25055.70c -0.0156126
14028.70c -0.007171335558
14029.70c -0.000377356542
14030.70c -0.0002576079
24050.70c -0.006190885148
24052.70c -0.124142524198
24053.70c -0.014348496148
24054.70c -0.003638294506
mt9 lwtr.10t
m10 1001.70c -0.0358870
8016.70c -0.2847761
5010.70c -1.15699e-4
5011.70c -5.27075e-4
26054.70c -0.02644016154
26056.70c -0.43037146399
26057.70c -0.0101152584
26058.70c -0.00137211607
28058.70c -0.04104621835
28060.70c -0.0163554502
28061.70c -0.000722605975
28062.70c -0.002342513875
28064.70c -0.0006157116
25055.70c -0.0135739
14028.70c -0.006234853554
14029.70c -0.000328078746
14030.70c -0.0002239677
24050.70c -0.005382452306
24052.70c -0.107931450781
24053.70c -0.012474806806
24054.70c -0.003163190107
mt10 lwtr.10t
m11 1001.70c -0.0162913
8016.70c -0.1292776
5010.70c -5.25228e-5
5011.70c -2.39272e-4
40090.70c -0.43313403903
40091.70c -0.09549277374
40092.70c -0.14759527104
40094.70c -0.15280552077
40096.70c -0.02511169542
mt11 lwtr.10t
m12 1001.70c -0.0292856
8016.70c -0.2323919
5010.70c -9.44159e-5
5011.70c -4.30120e-4
40090.70c -0.3741373658
40091.70c -0.0824858164
40092.70c -0.1274914944
40094.70c -0.1319920622
40096.70c -0.0216912612
mt12 lwtr.10t
kcode 10000 0.0 150 1150
sdef x=d1 y=d2 z=d3 erg=2
si1 -140 140
sp1 0 1
si2 -140 140
sp2 0 1
si3 -183 183
sp3 0 1

44
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#!/bin/bash
BASE_DIR=/opt/
##### DOWNLOAD DATA #####
mkdir -p $BASE_DIR/xdata && cd $BASE_DIR/xdata
wget -O endfb71.tar.xz https://anl.box.com/shared/static/9igk353zpy8fn9ttvtrqgzvw1vtejoz6.xz
tar -xf endfb71.tar.xz
wget -O endfb80.tar.xz https://anl.box.com/shared/static/uhbxlrx7hvxqw27psymfbhi7bx7s6u6a.xz
tar -xf endfb80.tar.xz
wget -O jeff33.tar.xz https://anl.box.com/shared/static/4jwkvrr9pxlruuihcrgti75zde6g7bum.xz
tar -xf jeff33.tar.xz
wget -O lib80x.tar.xz https://anl.box.com/shared/static/nd7p4jherolkx4b1rfaw5uqp58nxtstr.xz
tar -xf lib80x.tar.xz
wget -O fendl32.tar.xz https://anl.box.com/shared/static/3cb7jetw7tmxaw6nvn77x6c578jnm2ey.xz
tar -xf fendl32.tar.xz
git clone https://github.com/ahmedkmadani/OpenMCProject.git openmc-test
#########################
module load gcc/10.2.0
module load openmpi/4.1.4
module load python/miniconda23.5.2
source /share/apps/python/miniconda23.5.2/etc/profile.d/conda.sh
conda info --envs
conda create -n openmc-env
conda activate openmc-env
conda install -c conda-forge openmc (nodagmc_nompi_py311h86d942f_0)
conda list
conda search openmc
conda search openmc --channel conda-forge
echo $OPENMC_CROSS_SECTIONS
python --version
## ADD %env OPENMC_CROSS_SECTIONS /opt/xdata/endfb-vii.1-hdf5/cross_sections.xml
## to the top of any Notebook files you use
openmc -g -n 1000000 -s 32 -t -e problem

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<?xml version="1.0"?>
<geometry>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 1, Case 1
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<!-- surfaces for pin cell -->
<surface id="10" type="z-cylinder" coeffs="0. 0. 0.44" />
<surface id="11" type="z-cylinder" coeffs="0. 0. 0.49" />
<!-- surfaces for lattices -->
<surface id="20" type="x-plane" coeffs="-13.0" />
<surface id="21" type="x-plane" coeffs="-10.5" />
<surface id="22" type="x-plane" coeffs=" 10.5" />
<surface id="23" type="x-plane" coeffs=" 13.0" />
<surface id="30" type="y-plane" coeffs="-13.0" />
<surface id="31" type="y-plane" coeffs="-10.5" />
<surface id="32" type="y-plane" coeffs=" 10.5" />
<surface id="33" type="y-plane" coeffs=" 13.0" />
<!-- surfaces for overall geometry -->
<surface id="40" type="x-plane" coeffs="-40." boundary="vacuum" />
<surface id="41" type="x-plane" coeffs="0." />
<surface id="42" type="x-plane" coeffs="648." />
<surface id="43" type="x-plane" coeffs="688." boundary="vacuum" />
<surface id="50" type="y-plane" coeffs="-30." boundary="vacuum" />
<surface id="51" type="y-plane" coeffs="0." />
<surface id="52" type="y-plane" coeffs="81." />
<surface id="53" type="y-plane" coeffs="121." boundary="vacuum" />
<surface id="60" type="z-plane" coeffs="-30." boundary="vacuum" />
<surface id="61" type="z-plane" coeffs="0." />
<surface id="62" type="z-plane" coeffs="360." />
<surface id="63" type="z-plane" coeffs="390." boundary="vacuum" />
<!-- pin cell in water -->
<cell id="1" universe="3" material="1" region=" -10" />
<cell id="2" universe="3" material="2" region="10 -11" />
<cell id="3" universe="3" material="3" region="11" />
<!-- water assembly -->
<cell id="10" universe="1" material="4" region=" -20 " /> <!-- box -->
<cell id="11" universe="1" material="4" region="20 -23 -30" /> <!-- box -->
<cell id="12" universe="1" material="3" region="20 -23 30 -33" /> <!-- water -->
<cell id="13" universe="1" material="4" region="20 -23 33 " /> <!-- box -->
<cell id="14" universe="1" material="4" region="23 " /> <!-- box -->
<!-- fuel assembly -->
<cell id="20" universe="2" material="4" region=" -20 " /> <!-- box -->
<cell id="21" universe="2" material="4" region="20 -23 -30" /> <!-- box -->
<cell id="22" universe="2" material="3" region="20 -23 30 -31" /> <!-- water -->
<cell id="23" universe="2" material="3" region="20 -21 31 -32" /> <!-- water -->
<cell id="24" universe="2" fill="200" region="21 -22 31 -32" /> <!-- fuel -->
<cell id="25" universe="2" material="3" region="22 -23 31 -32" /> <!-- water -->
<cell id="26" universe="2" material="3" region="20 -23 32 -33" /> <!-- water -->
<cell id="27" universe="2" material="4" region="20 -23 33 " /> <!-- box -->
<cell id="28" universe="2" material="4" region="23 " /> <!-- box -->
<!-- checkerboard and surrounding materials -->
<cell id="31" material="5" region="40 -41 50 -53 60 -63" /> <!-- left concrete -->
<cell id="32" material="3" region="41 -42 50 -51 60 -63" /> <!-- bottom water (x,y plane) -->
<cell id="33" material="3" region="41 -42 51 -52 60 -61" /> <!-- bottom water (y,x plane) -->
<cell id="34" fill="100" region="41 -42 51 -52 61 -62" /> <!-- checkerboard -->
<cell id="35" material="3" region="41 -42 51 -52 62 -63" /> <!-- top water (y,x plane) -->
<cell id="36" material="5" region="41 -42 52 -53 60 -63" /> <!-- top concrete -->
<cell id="37" material="5" region="42 -43 50 -53 60 -63" /> <!-- right concrete -->
<lattice id="200" dimension="15 15" lower_left="-10.5 -10.5" pitch="1.4 1.4">
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
</universes>
</lattice>
<lattice id="100" dimension="24 3" lower_left="0. 0." pitch="27. 27.">
<universes>
2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1
1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2
2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1 2 1
</universes>
</lattice>
</geometry>

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@ -0,0 +1,66 @@
<?xml version="1.0"?>
<materials>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 1, Case 1
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<!-- UO2 fuel -->
<material id="1">
<density value="0.06925613" units="atom/b-cm" />
<nuclide name="U235" ao="2.2380e-02" />
<nuclide name="U238" ao="8.2213e-04" />
<nuclide name="O16" ao="4.6054e-02" />
</material>
<!-- Zirconium Clad -->
<material id="2">
<density value="4.2910e-02" units="atom/b-cm" />
<nuclide name="Zr90" ao="2.2077e-02" />
<nuclide name="Zr91" ao="4.8145e-03" />
<nuclide name="Zr92" ao="7.3591e-03" />
<nuclide name="Zr94" ao="7.4578e-03" />
<nuclide name="Zr96" ao="1.2015e-03" />
</material>
<!-- Water -->
<material id="3">
<density value="0.100059" units="atom/b-cm" />
<nuclide name="H1" ao="6.6706e-02" />
<nuclide name="O16" ao="3.3353e-02" />
<sab name="c_H_in_H2O" />
</material>
<!-- Iron -->
<material id="4">
<density value="8.3770e-02" units="atom/b-cm" />
<nuclide name="Fe54" ao="4.8964e-03" />
<nuclide name="Fe56" ao="7.6862e-02" />
<nuclide name="Fe57" ao="1.7751e-03" />
<nuclide name="Fe58" ao="2.3623e-04" />
</material>
<!-- Concrete -->
<material id="5">
<density value="0.0725757" units="atom/b-cm" />
<nuclide name="H1" ao="5.5437e-03" />
<nuclide name="C0" ao="6.9793e-03" />
<nuclide name="Si28" ao="7.1115e-03" />
<nuclide name="Si29" ao="3.6110e-04" />
<nuclide name="Si30" ao="2.3804e-04" />
<nuclide name="Ca40" ao="8.6850e-03" />
<nuclide name="Ca42" ao="5.7965e-05" />
<nuclide name="Ca43" ao="1.2095e-05" />
<nuclide name="Ca44" ao="1.8689e-04" />
<nuclide name="Ca46" ao="3.5836e-07" />
<nuclide name="Ca48" ao="1.6754e-05" />
<nuclide name="O16" ao="4.3383e-02" />
<sab name="c_H_in_H2O" />
</material>
</materials>

View file

@ -0,0 +1,31 @@
<?xml version="1.0"?>
<plots>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 1, Case 1
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<plot id="1" color="mat">
<origin>324. 45. 100.</origin>
<width>728. 151.</width>
<pixels>3000 600</pixels>
</plot>
<plot id="2" color="mat">
<origin>324. 45. -20.</origin>
<width>728. 151.</width>
<pixels>3000 600</pixels>
</plot>
<plot id="3" color="mat">
<origin>324. 45. 380.</origin>
<width>728. 151.</width>
<pixels>3000 600</pixels>
</plot>
</plots>

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@ -0,0 +1,35 @@
<?xml version="1.0"?>
<settings>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 1, Case 1
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<run_mode>eigenvalue</run_mode>
<batches>520</batches>
<inactive>20</inactive>
<particles>10000</particles>
<source>
<space>
<type>box</type>
<parameters>
0. 0. 0.
648. 81. 360.
</parameters>
</space>
</source>
<mesh id="1">
<lower_left>0. 0. 0.</lower_left>
<upper_right>648. 81. 360.</upper_right>
<dimension>24 3 10</dimension>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

View file

@ -0,0 +1,57 @@
<?xml version="1.0"?>
<geometry>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2, Case 1_1
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.412" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-plane" coeffs="0." boundary="vacuum" />
<surface id="4" type="z-plane" coeffs="30." />
<surface id="5" type="z-plane" coeffs="31.75" />
<surface id="6" type="z-plane" coeffs="36.75" />
<surface id="7" type="z-plane" coeffs="41.75" />
<surface id="8" type="z-plane" coeffs="51.75" />
<surface id="9" type="z-plane" coeffs="71.75" />
<surface id="10" type="z-plane" coeffs="357.45" />
<surface id="11" type="z-plane" coeffs="377.45" />
<surface id="12" type="z-plane" coeffs="387.45" />
<surface id="13" type="z-plane" coeffs="392.45" />
<surface id="14" type="z-plane" coeffs="397.45" />
<surface id="15" type="z-plane" coeffs="399.2" />
<surface id="16" type="z-plane" coeffs="429.2" boundary="vacuum" />
<surface id="20" type="x-plane" coeffs="-0.665" boundary="reflective" />
<surface id="21" type="x-plane" coeffs="0.665" boundary="reflective" />
<surface id="22" type="y-plane" coeffs="-0.665" boundary="reflective" />
<surface id="23" type="y-plane" coeffs="0.665" boundary="reflective" />
<!-- Surrounding water -->
<cell id="1" material="1" region="20 -21 22 -23 3 -4" />
<cell id="2" material="1" region="20 -21 22 -23 4 -15 2" />
<cell id="3" material="1" region="20 -21 22 -23 15 -16" />
<!-- Cladding, end plugs -->
<cell id="4" material="2" region=" -2 4 -5" />
<cell id="5" material="2" region="1 -2 5 -14" />
<cell id="6" material="2" region=" -2 14 -15" />
<!-- Fuel regions 9->1 -->
<cell id="7" material="3" region="-1 5 -6" />
<cell id="8" material="3" region="-1 6 -7" />
<cell id="9" material="3" region="-1 7 -8" />
<cell id="10" material="3" region="-1 8 -9" />
<cell id="11" material="5" region="-1 9 -10" />
<cell id="12" material="3" region="-1 10 -11" />
<cell id="13" material="3" region="-1 11 -12" />
<cell id="14" material="3" region="-1 12 -13" />
<cell id="15" material="3" region="-1 13 -14" />
</geometry>

View file

@ -0,0 +1,238 @@
<?xml version="1.0"?>
<materials>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
NOTE THE FUEL DENSITIES NEED UPDATING
-->
<!-- Water, 25 deg.C -->
<material id="1">
<density value="0.099987" units="atom/b-cm" />
<nuclide name="H1" ao="6.6658e-02" />
<nuclide name="O16" ao="3.3329e-02" />
<sab name="c_H_in_H2O" />
</material>
<!-- Zircaloy-4 -->
<material id="2">
<density value="0.043206271" units="atom/b-cm" />
<nuclide name="Cr50" ao="3.2975e-06" />
<nuclide name="Cr52" ao="6.3588e-05" />
<nuclide name="Cr53" ao="7.2104e-06" />
<nuclide name="Cr54" ao="1.7948e-06" />
<nuclide name="Fe54" ao="8.6728e-06" />
<nuclide name="Fe56" ao="1.3614e-04" />
<nuclide name="Fe57" ao="3.1442e-06" />
<nuclide name="Fe58" ao="4.1843e-07" />
<nuclide name="Zr90" ao="2.2114e-02" />
<nuclide name="Zr91" ao="4.8226e-03" />
<nuclide name="Zr92" ao="7.3714e-03" />
<nuclide name="Zr94" ao="7.4703e-03" />
<nuclide name="Zr96" ao="1.2035e-03" />
</material>
<!-- ====================== Fresh fuels =========================== -->
<!-- EU45: UO2, 4.5wt% enriched -->
<material id="3">
<density value="0.0693284852" units="atom/b-cm" />
<nuclide name="U234" ao="8.4100e-06" />
<nuclide name="U235" ao="1.0526e-03" />
<nuclide name="U236" ao="6.4752e-06" />
<nuclide name="U238" ao="2.2042e-02" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- EU40: UO2, 4.0wt% enriched -->
<material id="4">
<density value="0.0696080381" units="atom/b-cm" />
<nuclide name="U234" ao="7.5481e-06" />
<nuclide name="U235" ao="9.3949e-04" />
<nuclide name="U238" ao="2.2256e-02" />
<nuclide name="O16" ao="4.6405e-02" />
</material>
<!-- NU: UO2, Natural uranium -->
<material id="5">
<density value="0.0695822757" units="atom/b-cm" />
<nuclide name="U234" ao="1.2757e-06" />
<nuclide name="U235" ao="1.6700e-04" />
<nuclide name="U238" ao="2.3026e-02" />
<nuclide name="O16" ao="4.6388e-02" />
</material>
<!-- ===================== Burnup fuels =========================== -->
<!-- B21G, EU45, 21.570 GWD/MTU -->
<material id="6">
<density value="0.0690055" units="atom/b-cm" />
<nuclide name="U234" ao="6.4862e-06" />
<nuclide name="U235" ao="5.6758e-04" />
<nuclide name="U236" ao="9.4556e-05" />
<nuclide name="U238" ao="2.1732e-02" />
<nuclide name="Pu238" ao="1.1322e-06" />
<nuclide name="Pu239" ao="1.2591e-04" />
<nuclide name="Pu240" ao="2.6395e-05" />
<nuclide name="Pu241" ao="1.3614e-05" />
<nuclide name="Pu242" ao="2.2623e-06" />
<nuclide name="Am241" ao="4.0266e-06" />
<nuclide name="Am243" ao="2.6222e-07" />
<nuclide name="Np237" ao="6.8089e-06" />
<nuclide name="Mo95" ao="3.1530e-05" />
<nuclide name="Tc99" ao="3.0319e-05" />
<nuclide name="Ru101" ao="2.7452e-05" />
<nuclide name="Rh103" ao="1.7260e-05" />
<nuclide name="Ag109" ao="1.8879e-06" />
<nuclide name="Cs133" ao="3.3140e-05" />
<nuclide name="Sm147" ao="6.4488e-06" />
<nuclide name="Sm149" ao="1.9390e-07" />
<nuclide name="Sm150" ao="7.1174e-06" />
<nuclide name="Sm151" ao="5.7531e-07" />
<nuclide name="Sm152" ao="3.0178e-06" />
<nuclide name="Nd143" ao="2.5793e-05" />
<nuclide name="Nd145" ao="1.8633e-05" />
<nuclide name="Eu153" ao="2.0026e-06" />
<nuclide name="Gd155" ao="1.1986e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B24G, EU45, 24.023 GWD/MTU -->
<material id="7">
<density value="0.0689673" units="atom/b-cm" />
<nuclide name="U234" ao="6.2881e-06" />
<nuclide name="U235" ao="5.2562e-04" />
<nuclide name="U236" ao="1.0155e-04" />
<nuclide name="U238" ao="2.1693e-02" />
<nuclide name="Pu238" ao="1.4876e-06" />
<nuclide name="Pu239" ao="1.3161e-04" />
<nuclide name="Pu240" ao="2.9965e-05" />
<nuclide name="Pu241" ao="1.5953e-05" />
<nuclide name="Pu242" ao="3.0335e-06" />
<nuclide name="Am241" ao="4.7603e-06" />
<nuclide name="Am243" ao="3.9809e-07" />
<nuclide name="Np237" ao="7.9041e-06" />
<nuclide name="Mo95" ao="3.4781e-05" />
<nuclide name="Tc99" ao="3.3465e-05" />
<nuclide name="Ru101" ao="3.0548e-05" />
<nuclide name="Rh103" ao="1.9008e-05" />
<nuclide name="Ag109" ao="2.2230e-06" />
<nuclide name="Cs133" ao="3.6549e-05" />
<nuclide name="Sm147" ao="6.9339e-06" />
<nuclide name="Sm149" ao="1.9611e-07" />
<nuclide name="Sm150" ao="8.0472e-06" />
<nuclide name="Sm151" ao="6.0064e-07" />
<nuclide name="Sm152" ao="3.3473e-06" />
<nuclide name="Nd143" ao="2.8067e-05" />
<nuclide name="Nd145" ao="2.0504e-05" />
<nuclide name="Eu153" ao="2.3329e-06" />
<nuclide name="Gd155" ao="1.4386e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B30G, EU45, 30.580 GWD/MTU -->
<material id="8">
<density value="0.0688634" units="atom/b-cm" />
<nuclide name="U234" ao="5.7868e-06" />
<nuclide name="U235" ao="4.2455e-04" />
<nuclide name="U236" ao="1.1763e-04" />
<nuclide name="U238" ao="2.1585e-02" />
<nuclide name="Pu238" ao="2.7262e-06" />
<nuclide name="Pu239" ao="1.4249e-04" />
<nuclide name="Pu240" ao="3.9140e-05" />
<nuclide name="Pu241" ao="2.1863e-05" />
<nuclide name="Pu242" ao="5.6472e-06" />
<nuclide name="Am241" ao="6.6579e-06" />
<nuclide name="Am243" ao="9.7353e-07" />
<nuclide name="Np237" ao="1.0948e-05" />
<nuclide name="Mo95" ao="4.3130e-05" />
<nuclide name="Tc99" ao="4.1531e-05" />
<nuclide name="Ru101" ao="3.8751e-05" />
<nuclide name="Rh103" ao="2.3371e-05" />
<nuclide name="Ag109" ao="3.1774e-06" />
<nuclide name="Cs133" ao="4.5257e-05" />
<nuclide name="Sm147" ao="8.0315e-06" />
<nuclide name="Sm149" ao="1.9935e-07" />
<nuclide name="Sm150" ao="1.0496e-05" />
<nuclide name="Sm151" ao="6.6160e-07" />
<nuclide name="Sm152" ao="4.1844e-06" />
<nuclide name="Nd143" ao="3.3502e-05" />
<nuclide name="Nd145" ao="2.5263e-05" />
<nuclide name="Eu153" ao="3.2546e-06" />
<nuclide name="Gd155" ao="2.2155e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU45, 40.424 GWD/MTU -->
<material id="9">
<density value="0.0687030" units="atom/b-cm" />
<nuclide name="U234" ao="5.1152e-06" />
<nuclide name="U235" ao="3.0002e-04" />
<nuclide name="U236" ao="1.3534e-04" />
<nuclide name="U238" ao="2.1413e-02" />
<nuclide name="Pu238" ao="5.3656e-06" />
<nuclide name="Pu239" ao="1.5064e-04" />
<nuclide name="Pu240" ao="5.1484e-05" />
<nuclide name="Pu241" ao="2.9175e-05" />
<nuclide name="Pu242" ao="1.0893e-05" />
<nuclide name="Am241" ao="9.0866e-06" />
<nuclide name="Am243" ao="2.5108e-06" />
<nuclide name="Np237" ao="1.5602e-05" />
<nuclide name="Mo95" ao="5.4806e-05" />
<nuclide name="Tc99" ao="5.2746e-05" />
<nuclide name="Ru101" ao="5.0881e-05" />
<nuclide name="Rh103" ao="2.9057e-05" />
<nuclide name="Ag109" ao="4.7134e-06" />
<nuclide name="Cs133" ao="5.7263e-05" />
<nuclide name="Sm147" ao="9.2075e-06" />
<nuclide name="Sm149" ao="1.9993e-07" />
<nuclide name="Sm150" ao="1.3997e-05" />
<nuclide name="Sm151" ao="7.3765e-07" />
<nuclide name="Sm152" ao="5.3316e-06" />
<nuclide name="Nd143" ao="3.9984e-05" />
<nuclide name="Nd145" ao="3.1783e-05" />
<nuclide name="Eu153" ao="4.6705e-06" />
<nuclide name="Gd155" ao="3.6871e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU55, 54.605 GWD/MTU -->
<material id="10">
<density value="0.06845907" units="atom/b-cm" />
<nuclide name="U234" ao="4.3280e-06" />
<nuclide name="U235" ao="1.7108e-04" />
<nuclide name="U236" ao="1.4897e-04" />
<nuclide name="U238" ao="2.1142e-02" />
<nuclide name="Pu238" ao="1.0471e-05" />
<nuclide name="Pu239" ao="1.5300e-04" />
<nuclide name="Pu240" ao="6.5540e-05" />
<nuclide name="Pu241" ao="3.6032e-05" />
<nuclide name="Pu242" ao="2.0303e-05" />
<nuclide name="Am241" ao="1.1405e-05" />
<nuclide name="Am243" ao="6.1550e-06" />
<nuclide name="Np237" ao="2.1806e-05" />
<nuclide name="Mo95" ao="6.9892e-05" />
<nuclide name="Tc99" ao="6.6975e-05" />
<nuclide name="Ru101" ao="6.7875e-05" />
<nuclide name="Rh103" ao="3.5406e-05" />
<nuclide name="Ag109" ao="6.9836e-06" />
<nuclide name="Cs133" ao="7.2263e-05" />
<nuclide name="Sm147" ao="1.0106e-05" />
<nuclide name="Sm149" ao="1.9259e-07" />
<nuclide name="Sm150" ao="1.8627e-05" />
<nuclide name="Sm151" ao="8.1779e-07" />
<nuclide name="Sm152" ao="6.7637e-06" />
<nuclide name="Nd143" ao="4.5992e-05" />
<nuclide name="Nd145" ao="3.9892e-05" />
<nuclide name="Eu153" ao="6.5858e-06" />
<nuclide name="Gd155" ao="6.0862e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
</materials>

View file

@ -0,0 +1,35 @@
<?xml version="1.0"?>
<settings>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<run_mode>eigenvalue</run_mode>
<batches>1200</batches>
<inactive>200</inactive>
<particles>10000</particles>
<source>
<space>
<type>box</type>
<parameters>
-0.665 -0.665 0.
0.665 0.665 429.2
</parameters>
</space>
</source>
<mesh id="1">
<lower_left>-0.665 -0.665 0.</lower_left>
<upper_right>0.665 0.665 429.2</upper_right>
<dimension>1 1 400</dimension>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

View file

@ -0,0 +1,57 @@
<?xml version="1.0"?>
<geometry>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2, Case 1_2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.412" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-plane" coeffs="0." boundary="vacuum" />
<surface id="4" type="z-plane" coeffs="30." />
<surface id="5" type="z-plane" coeffs="31.75" />
<surface id="6" type="z-plane" coeffs="36.75" />
<surface id="7" type="z-plane" coeffs="41.75" />
<surface id="8" type="z-plane" coeffs="51.75" />
<surface id="9" type="z-plane" coeffs="71.75" />
<surface id="10" type="z-plane" coeffs="357.45" />
<surface id="11" type="z-plane" coeffs="377.45" />
<surface id="12" type="z-plane" coeffs="387.45" />
<surface id="13" type="z-plane" coeffs="392.45" />
<surface id="14" type="z-plane" coeffs="397.45" />
<surface id="15" type="z-plane" coeffs="399.2" />
<surface id="16" type="z-plane" coeffs="429.2" boundary="vacuum" />
<surface id="20" type="x-plane" coeffs="-0.665" boundary="reflective" />
<surface id="21" type="x-plane" coeffs="0.665" boundary="reflective" />
<surface id="22" type="y-plane" coeffs="-0.665" boundary="reflective" />
<surface id="23" type="y-plane" coeffs="0.665" boundary="reflective" />
<!-- Surrounding water -->
<cell id="1" material="1" region="20 -21 22 -23 3 -4" />
<cell id="2" material="1" region="20 -21 22 -23 4 -15 2" />
<cell id="3" material="1" region="20 -21 22 -23 15 -16" />
<!-- Cladding, end plugs -->
<cell id="4" material="2" region=" -2 4 -5" />
<cell id="5" material="2" region="1 -2 5 -14" />
<cell id="6" material="2" region=" -2 14 -15" />
<!-- Fuel regions 9->1 -->
<cell id="7" material="4" region="-1 5 -6" />
<cell id="8" material="4" region="-1 6 -7" />
<cell id="9" material="4" region="-1 7 -8" />
<cell id="10" material="4" region="-1 8 -9" />
<cell id="11" material="5" region="-1 9 -10" />
<cell id="12" material="3" region="-1 10 -11" />
<cell id="13" material="3" region="-1 11 -12" />
<cell id="14" material="3" region="-1 12 -13" />
<cell id="15" material="3" region="-1 13 -14" />
</geometry>

View file

@ -0,0 +1,238 @@
<?xml version="1.0"?>
<materials>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
NOTE THE FUEL DENSITIES NEED UPDATING
-->
<!-- Water, 25 deg.C -->
<material id="1">
<density value="0.099987" units="atom/b-cm" />
<nuclide name="H1" ao="6.6658e-02" />
<nuclide name="O16" ao="3.3329e-02" />
<sab name="c_H_in_H2O" />
</material>
<!-- Zircaloy-4 -->
<material id="2">
<density value="0.043206271" units="atom/b-cm" />
<nuclide name="Cr50" ao="3.2975e-06" />
<nuclide name="Cr52" ao="6.3588e-05" />
<nuclide name="Cr53" ao="7.2104e-06" />
<nuclide name="Cr54" ao="1.7948e-06" />
<nuclide name="Fe54" ao="8.6728e-06" />
<nuclide name="Fe56" ao="1.3614e-04" />
<nuclide name="Fe57" ao="3.1442e-06" />
<nuclide name="Fe58" ao="4.1843e-07" />
<nuclide name="Zr90" ao="2.2114e-02" />
<nuclide name="Zr91" ao="4.8226e-03" />
<nuclide name="Zr92" ao="7.3714e-03" />
<nuclide name="Zr94" ao="7.4703e-03" />
<nuclide name="Zr96" ao="1.2035e-03" />
</material>
<!-- ====================== Fresh fuels =========================== -->
<!-- EU45: UO2, 4.5wt% enriched -->
<material id="3">
<density value="0.0693284852" units="atom/b-cm" />
<nuclide name="U234" ao="8.4100e-06" />
<nuclide name="U235" ao="1.0526e-03" />
<nuclide name="U236" ao="6.4752e-06" />
<nuclide name="U238" ao="2.2042e-02" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- EU40: UO2, 4.0wt% enriched -->
<material id="4">
<density value="0.0696080381" units="atom/b-cm" />
<nuclide name="U234" ao="7.5481e-06" />
<nuclide name="U235" ao="9.3949e-04" />
<nuclide name="U238" ao="2.2256e-02" />
<nuclide name="O16" ao="4.6405e-02" />
</material>
<!-- NU: UO2, Natural uranium -->
<material id="5">
<density value="0.0695822757" units="atom/b-cm" />
<nuclide name="U234" ao="1.2757e-06" />
<nuclide name="U235" ao="1.6700e-04" />
<nuclide name="U238" ao="2.3026e-02" />
<nuclide name="O16" ao="4.6388e-02" />
</material>
<!-- ===================== Burnup fuels =========================== -->
<!-- B21G, EU45, 21.570 GWD/MTU -->
<material id="6">
<density value="0.0690055" units="atom/b-cm" />
<nuclide name="U234" ao="6.4862e-06" />
<nuclide name="U235" ao="5.6758e-04" />
<nuclide name="U236" ao="9.4556e-05" />
<nuclide name="U238" ao="2.1732e-02" />
<nuclide name="Pu238" ao="1.1322e-06" />
<nuclide name="Pu239" ao="1.2591e-04" />
<nuclide name="Pu240" ao="2.6395e-05" />
<nuclide name="Pu241" ao="1.3614e-05" />
<nuclide name="Pu242" ao="2.2623e-06" />
<nuclide name="Am241" ao="4.0266e-06" />
<nuclide name="Am243" ao="2.6222e-07" />
<nuclide name="Np237" ao="6.8089e-06" />
<nuclide name="Mo95" ao="3.1530e-05" />
<nuclide name="Tc99" ao="3.0319e-05" />
<nuclide name="Ru101" ao="2.7452e-05" />
<nuclide name="Rh103" ao="1.7260e-05" />
<nuclide name="Ag109" ao="1.8879e-06" />
<nuclide name="Cs133" ao="3.3140e-05" />
<nuclide name="Sm147" ao="6.4488e-06" />
<nuclide name="Sm149" ao="1.9390e-07" />
<nuclide name="Sm150" ao="7.1174e-06" />
<nuclide name="Sm151" ao="5.7531e-07" />
<nuclide name="Sm152" ao="3.0178e-06" />
<nuclide name="Nd143" ao="2.5793e-05" />
<nuclide name="Nd145" ao="1.8633e-05" />
<nuclide name="Eu153" ao="2.0026e-06" />
<nuclide name="Gd155" ao="1.1986e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B24G, EU45, 24.023 GWD/MTU -->
<material id="7">
<density value="0.0689673" units="atom/b-cm" />
<nuclide name="U234" ao="6.2881e-06" />
<nuclide name="U235" ao="5.2562e-04" />
<nuclide name="U236" ao="1.0155e-04" />
<nuclide name="U238" ao="2.1693e-02" />
<nuclide name="Pu238" ao="1.4876e-06" />
<nuclide name="Pu239" ao="1.3161e-04" />
<nuclide name="Pu240" ao="2.9965e-05" />
<nuclide name="Pu241" ao="1.5953e-05" />
<nuclide name="Pu242" ao="3.0335e-06" />
<nuclide name="Am241" ao="4.7603e-06" />
<nuclide name="Am243" ao="3.9809e-07" />
<nuclide name="Np237" ao="7.9041e-06" />
<nuclide name="Mo95" ao="3.4781e-05" />
<nuclide name="Tc99" ao="3.3465e-05" />
<nuclide name="Ru101" ao="3.0548e-05" />
<nuclide name="Rh103" ao="1.9008e-05" />
<nuclide name="Ag109" ao="2.2230e-06" />
<nuclide name="Cs133" ao="3.6549e-05" />
<nuclide name="Sm147" ao="6.9339e-06" />
<nuclide name="Sm149" ao="1.9611e-07" />
<nuclide name="Sm150" ao="8.0472e-06" />
<nuclide name="Sm151" ao="6.0064e-07" />
<nuclide name="Sm152" ao="3.3473e-06" />
<nuclide name="Nd143" ao="2.8067e-05" />
<nuclide name="Nd145" ao="2.0504e-05" />
<nuclide name="Eu153" ao="2.3329e-06" />
<nuclide name="Gd155" ao="1.4386e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B30G, EU45, 30.580 GWD/MTU -->
<material id="8">
<density value="0.0688634" units="atom/b-cm" />
<nuclide name="U234" ao="5.7868e-06" />
<nuclide name="U235" ao="4.2455e-04" />
<nuclide name="U236" ao="1.1763e-04" />
<nuclide name="U238" ao="2.1585e-02" />
<nuclide name="Pu238" ao="2.7262e-06" />
<nuclide name="Pu239" ao="1.4249e-04" />
<nuclide name="Pu240" ao="3.9140e-05" />
<nuclide name="Pu241" ao="2.1863e-05" />
<nuclide name="Pu242" ao="5.6472e-06" />
<nuclide name="Am241" ao="6.6579e-06" />
<nuclide name="Am243" ao="9.7353e-07" />
<nuclide name="Np237" ao="1.0948e-05" />
<nuclide name="Mo95" ao="4.3130e-05" />
<nuclide name="Tc99" ao="4.1531e-05" />
<nuclide name="Ru101" ao="3.8751e-05" />
<nuclide name="Rh103" ao="2.3371e-05" />
<nuclide name="Ag109" ao="3.1774e-06" />
<nuclide name="Cs133" ao="4.5257e-05" />
<nuclide name="Sm147" ao="8.0315e-06" />
<nuclide name="Sm149" ao="1.9935e-07" />
<nuclide name="Sm150" ao="1.0496e-05" />
<nuclide name="Sm151" ao="6.6160e-07" />
<nuclide name="Sm152" ao="4.1844e-06" />
<nuclide name="Nd143" ao="3.3502e-05" />
<nuclide name="Nd145" ao="2.5263e-05" />
<nuclide name="Eu153" ao="3.2546e-06" />
<nuclide name="Gd155" ao="2.2155e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU45, 40.424 GWD/MTU -->
<material id="9">
<density value="0.0687030" units="atom/b-cm" />
<nuclide name="U234" ao="5.1152e-06" />
<nuclide name="U235" ao="3.0002e-04" />
<nuclide name="U236" ao="1.3534e-04" />
<nuclide name="U238" ao="2.1413e-02" />
<nuclide name="Pu238" ao="5.3656e-06" />
<nuclide name="Pu239" ao="1.5064e-04" />
<nuclide name="Pu240" ao="5.1484e-05" />
<nuclide name="Pu241" ao="2.9175e-05" />
<nuclide name="Pu242" ao="1.0893e-05" />
<nuclide name="Am241" ao="9.0866e-06" />
<nuclide name="Am243" ao="2.5108e-06" />
<nuclide name="Np237" ao="1.5602e-05" />
<nuclide name="Mo95" ao="5.4806e-05" />
<nuclide name="Tc99" ao="5.2746e-05" />
<nuclide name="Ru101" ao="5.0881e-05" />
<nuclide name="Rh103" ao="2.9057e-05" />
<nuclide name="Ag109" ao="4.7134e-06" />
<nuclide name="Cs133" ao="5.7263e-05" />
<nuclide name="Sm147" ao="9.2075e-06" />
<nuclide name="Sm149" ao="1.9993e-07" />
<nuclide name="Sm150" ao="1.3997e-05" />
<nuclide name="Sm151" ao="7.3765e-07" />
<nuclide name="Sm152" ao="5.3316e-06" />
<nuclide name="Nd143" ao="3.9984e-05" />
<nuclide name="Nd145" ao="3.1783e-05" />
<nuclide name="Eu153" ao="4.6705e-06" />
<nuclide name="Gd155" ao="3.6871e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU55, 54.605 GWD/MTU -->
<material id="10">
<density value="0.06845907" units="atom/b-cm" />
<nuclide name="U234" ao="4.3280e-06" />
<nuclide name="U235" ao="1.7108e-04" />
<nuclide name="U236" ao="1.4897e-04" />
<nuclide name="U238" ao="2.1142e-02" />
<nuclide name="Pu238" ao="1.0471e-05" />
<nuclide name="Pu239" ao="1.5300e-04" />
<nuclide name="Pu240" ao="6.5540e-05" />
<nuclide name="Pu241" ao="3.6032e-05" />
<nuclide name="Pu242" ao="2.0303e-05" />
<nuclide name="Am241" ao="1.1405e-05" />
<nuclide name="Am243" ao="6.1550e-06" />
<nuclide name="Np237" ao="2.1806e-05" />
<nuclide name="Mo95" ao="6.9892e-05" />
<nuclide name="Tc99" ao="6.6975e-05" />
<nuclide name="Ru101" ao="6.7875e-05" />
<nuclide name="Rh103" ao="3.5406e-05" />
<nuclide name="Ag109" ao="6.9836e-06" />
<nuclide name="Cs133" ao="7.2263e-05" />
<nuclide name="Sm147" ao="1.0106e-05" />
<nuclide name="Sm149" ao="1.9259e-07" />
<nuclide name="Sm150" ao="1.8627e-05" />
<nuclide name="Sm151" ao="8.1779e-07" />
<nuclide name="Sm152" ao="6.7637e-06" />
<nuclide name="Nd143" ao="4.5992e-05" />
<nuclide name="Nd145" ao="3.9892e-05" />
<nuclide name="Eu153" ao="6.5858e-06" />
<nuclide name="Gd155" ao="6.0862e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
</materials>

View file

@ -0,0 +1,35 @@
<?xml version="1.0"?>
<settings>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<run_mode>eigenvalue</run_mode>
<batches>1200</batches>
<inactive>200</inactive>
<particles>10000</particles>
<source>
<space>
<type>box</type>
<parameters>
-0.665 -0.665 0.
0.665 0.665 429.2
</parameters>
</space>
</source>
<mesh id="1">
<lower_left>-0.665 -0.665 0.</lower_left>
<upper_right>0.665 0.665 429.2</upper_right>
<dimension>1 1 400</dimension>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

View file

@ -0,0 +1,57 @@
<?xml version="1.0"?>
<geometry>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2, Case 1_3
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.412" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-plane" coeffs="0." boundary="vacuum" />
<surface id="4" type="z-plane" coeffs="30." />
<surface id="5" type="z-plane" coeffs="31.75" />
<surface id="6" type="z-plane" coeffs="36.75" />
<surface id="7" type="z-plane" coeffs="41.75" />
<surface id="8" type="z-plane" coeffs="51.75" />
<surface id="9" type="z-plane" coeffs="71.75" />
<surface id="10" type="z-plane" coeffs="357.45" />
<surface id="11" type="z-plane" coeffs="377.45" />
<surface id="12" type="z-plane" coeffs="387.45" />
<surface id="13" type="z-plane" coeffs="392.45" />
<surface id="14" type="z-plane" coeffs="397.45" />
<surface id="15" type="z-plane" coeffs="399.2" />
<surface id="16" type="z-plane" coeffs="429.2" boundary="vacuum" />
<surface id="20" type="x-plane" coeffs="-0.665" boundary="reflective" />
<surface id="21" type="x-plane" coeffs="0.665" boundary="reflective" />
<surface id="22" type="y-plane" coeffs="-0.665" boundary="reflective" />
<surface id="23" type="y-plane" coeffs="0.665" boundary="reflective" />
<!-- Surrounding water -->
<cell id="1" material="1" region="20 -21 22 -23 3 -4" />
<cell id="2" material="1" region="20 -21 22 -23 4 -15 2" />
<cell id="3" material="1" region="20 -21 22 -23 15 -16" />
<!-- Cladding, end plugs -->
<cell id="4" material="2" region=" -2 4 -5" />
<cell id="5" material="2" region="1 -2 5 -14" />
<cell id="6" material="2" region=" -2 14 -15" />
<!-- Fuel regions 9->1 -->
<cell id="7" material="4" region="-1 5 -6" />
<cell id="8" material="4" region="-1 6 -7" />
<cell id="9" material="3" region="-1 7 -8" />
<cell id="10" material="3" region="-1 8 -9" />
<cell id="11" material="5" region="-1 9 -10" />
<cell id="12" material="3" region="-1 10 -11" />
<cell id="13" material="3" region="-1 11 -12" />
<cell id="14" material="3" region="-1 12 -13" />
<cell id="15" material="3" region="-1 13 -14" />
</geometry>

View file

@ -0,0 +1,238 @@
<?xml version="1.0"?>
<materials>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
NOTE THE FUEL DENSITIES NEED UPDATING
-->
<!-- Water, 25 deg.C -->
<material id="1">
<density value="0.099987" units="atom/b-cm" />
<nuclide name="H1" ao="6.6658e-02" />
<nuclide name="O16" ao="3.3329e-02" />
<sab name="c_H_in_H2O" />
</material>
<!-- Zircaloy-4 -->
<material id="2">
<density value="0.043206271" units="atom/b-cm" />
<nuclide name="Cr50" ao="3.2975e-06" />
<nuclide name="Cr52" ao="6.3588e-05" />
<nuclide name="Cr53" ao="7.2104e-06" />
<nuclide name="Cr54" ao="1.7948e-06" />
<nuclide name="Fe54" ao="8.6728e-06" />
<nuclide name="Fe56" ao="1.3614e-04" />
<nuclide name="Fe57" ao="3.1442e-06" />
<nuclide name="Fe58" ao="4.1843e-07" />
<nuclide name="Zr90" ao="2.2114e-02" />
<nuclide name="Zr91" ao="4.8226e-03" />
<nuclide name="Zr92" ao="7.3714e-03" />
<nuclide name="Zr94" ao="7.4703e-03" />
<nuclide name="Zr96" ao="1.2035e-03" />
</material>
<!-- ====================== Fresh fuels =========================== -->
<!-- EU45: UO2, 4.5wt% enriched -->
<material id="3">
<density value="0.0693284852" units="atom/b-cm" />
<nuclide name="U234" ao="8.4100e-06" />
<nuclide name="U235" ao="1.0526e-03" />
<nuclide name="U236" ao="6.4752e-06" />
<nuclide name="U238" ao="2.2042e-02" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- EU40: UO2, 4.0wt% enriched -->
<material id="4">
<density value="0.0696080381" units="atom/b-cm" />
<nuclide name="U234" ao="7.5481e-06" />
<nuclide name="U235" ao="9.3949e-04" />
<nuclide name="U238" ao="2.2256e-02" />
<nuclide name="O16" ao="4.6405e-02" />
</material>
<!-- NU: UO2, Natural uranium -->
<material id="5">
<density value="0.0695822757" units="atom/b-cm" />
<nuclide name="U234" ao="1.2757e-06" />
<nuclide name="U235" ao="1.6700e-04" />
<nuclide name="U238" ao="2.3026e-02" />
<nuclide name="O16" ao="4.6388e-02" />
</material>
<!-- ===================== Burnup fuels =========================== -->
<!-- B21G, EU45, 21.570 GWD/MTU -->
<material id="6">
<density value="0.0690055" units="atom/b-cm" />
<nuclide name="U234" ao="6.4862e-06" />
<nuclide name="U235" ao="5.6758e-04" />
<nuclide name="U236" ao="9.4556e-05" />
<nuclide name="U238" ao="2.1732e-02" />
<nuclide name="Pu238" ao="1.1322e-06" />
<nuclide name="Pu239" ao="1.2591e-04" />
<nuclide name="Pu240" ao="2.6395e-05" />
<nuclide name="Pu241" ao="1.3614e-05" />
<nuclide name="Pu242" ao="2.2623e-06" />
<nuclide name="Am241" ao="4.0266e-06" />
<nuclide name="Am243" ao="2.6222e-07" />
<nuclide name="Np237" ao="6.8089e-06" />
<nuclide name="Mo95" ao="3.1530e-05" />
<nuclide name="Tc99" ao="3.0319e-05" />
<nuclide name="Ru101" ao="2.7452e-05" />
<nuclide name="Rh103" ao="1.7260e-05" />
<nuclide name="Ag109" ao="1.8879e-06" />
<nuclide name="Cs133" ao="3.3140e-05" />
<nuclide name="Sm147" ao="6.4488e-06" />
<nuclide name="Sm149" ao="1.9390e-07" />
<nuclide name="Sm150" ao="7.1174e-06" />
<nuclide name="Sm151" ao="5.7531e-07" />
<nuclide name="Sm152" ao="3.0178e-06" />
<nuclide name="Nd143" ao="2.5793e-05" />
<nuclide name="Nd145" ao="1.8633e-05" />
<nuclide name="Eu153" ao="2.0026e-06" />
<nuclide name="Gd155" ao="1.1986e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B24G, EU45, 24.023 GWD/MTU -->
<material id="7">
<density value="0.0689673" units="atom/b-cm" />
<nuclide name="U234" ao="6.2881e-06" />
<nuclide name="U235" ao="5.2562e-04" />
<nuclide name="U236" ao="1.0155e-04" />
<nuclide name="U238" ao="2.1693e-02" />
<nuclide name="Pu238" ao="1.4876e-06" />
<nuclide name="Pu239" ao="1.3161e-04" />
<nuclide name="Pu240" ao="2.9965e-05" />
<nuclide name="Pu241" ao="1.5953e-05" />
<nuclide name="Pu242" ao="3.0335e-06" />
<nuclide name="Am241" ao="4.7603e-06" />
<nuclide name="Am243" ao="3.9809e-07" />
<nuclide name="Np237" ao="7.9041e-06" />
<nuclide name="Mo95" ao="3.4781e-05" />
<nuclide name="Tc99" ao="3.3465e-05" />
<nuclide name="Ru101" ao="3.0548e-05" />
<nuclide name="Rh103" ao="1.9008e-05" />
<nuclide name="Ag109" ao="2.2230e-06" />
<nuclide name="Cs133" ao="3.6549e-05" />
<nuclide name="Sm147" ao="6.9339e-06" />
<nuclide name="Sm149" ao="1.9611e-07" />
<nuclide name="Sm150" ao="8.0472e-06" />
<nuclide name="Sm151" ao="6.0064e-07" />
<nuclide name="Sm152" ao="3.3473e-06" />
<nuclide name="Nd143" ao="2.8067e-05" />
<nuclide name="Nd145" ao="2.0504e-05" />
<nuclide name="Eu153" ao="2.3329e-06" />
<nuclide name="Gd155" ao="1.4386e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B30G, EU45, 30.580 GWD/MTU -->
<material id="8">
<density value="0.0688634" units="atom/b-cm" />
<nuclide name="U234" ao="5.7868e-06" />
<nuclide name="U235" ao="4.2455e-04" />
<nuclide name="U236" ao="1.1763e-04" />
<nuclide name="U238" ao="2.1585e-02" />
<nuclide name="Pu238" ao="2.7262e-06" />
<nuclide name="Pu239" ao="1.4249e-04" />
<nuclide name="Pu240" ao="3.9140e-05" />
<nuclide name="Pu241" ao="2.1863e-05" />
<nuclide name="Pu242" ao="5.6472e-06" />
<nuclide name="Am241" ao="6.6579e-06" />
<nuclide name="Am243" ao="9.7353e-07" />
<nuclide name="Np237" ao="1.0948e-05" />
<nuclide name="Mo95" ao="4.3130e-05" />
<nuclide name="Tc99" ao="4.1531e-05" />
<nuclide name="Ru101" ao="3.8751e-05" />
<nuclide name="Rh103" ao="2.3371e-05" />
<nuclide name="Ag109" ao="3.1774e-06" />
<nuclide name="Cs133" ao="4.5257e-05" />
<nuclide name="Sm147" ao="8.0315e-06" />
<nuclide name="Sm149" ao="1.9935e-07" />
<nuclide name="Sm150" ao="1.0496e-05" />
<nuclide name="Sm151" ao="6.6160e-07" />
<nuclide name="Sm152" ao="4.1844e-06" />
<nuclide name="Nd143" ao="3.3502e-05" />
<nuclide name="Nd145" ao="2.5263e-05" />
<nuclide name="Eu153" ao="3.2546e-06" />
<nuclide name="Gd155" ao="2.2155e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU45, 40.424 GWD/MTU -->
<material id="9">
<density value="0.0687030" units="atom/b-cm" />
<nuclide name="U234" ao="5.1152e-06" />
<nuclide name="U235" ao="3.0002e-04" />
<nuclide name="U236" ao="1.3534e-04" />
<nuclide name="U238" ao="2.1413e-02" />
<nuclide name="Pu238" ao="5.3656e-06" />
<nuclide name="Pu239" ao="1.5064e-04" />
<nuclide name="Pu240" ao="5.1484e-05" />
<nuclide name="Pu241" ao="2.9175e-05" />
<nuclide name="Pu242" ao="1.0893e-05" />
<nuclide name="Am241" ao="9.0866e-06" />
<nuclide name="Am243" ao="2.5108e-06" />
<nuclide name="Np237" ao="1.5602e-05" />
<nuclide name="Mo95" ao="5.4806e-05" />
<nuclide name="Tc99" ao="5.2746e-05" />
<nuclide name="Ru101" ao="5.0881e-05" />
<nuclide name="Rh103" ao="2.9057e-05" />
<nuclide name="Ag109" ao="4.7134e-06" />
<nuclide name="Cs133" ao="5.7263e-05" />
<nuclide name="Sm147" ao="9.2075e-06" />
<nuclide name="Sm149" ao="1.9993e-07" />
<nuclide name="Sm150" ao="1.3997e-05" />
<nuclide name="Sm151" ao="7.3765e-07" />
<nuclide name="Sm152" ao="5.3316e-06" />
<nuclide name="Nd143" ao="3.9984e-05" />
<nuclide name="Nd145" ao="3.1783e-05" />
<nuclide name="Eu153" ao="4.6705e-06" />
<nuclide name="Gd155" ao="3.6871e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU55, 54.605 GWD/MTU -->
<material id="10">
<density value="0.06845907" units="atom/b-cm" />
<nuclide name="U234" ao="4.3280e-06" />
<nuclide name="U235" ao="1.7108e-04" />
<nuclide name="U236" ao="1.4897e-04" />
<nuclide name="U238" ao="2.1142e-02" />
<nuclide name="Pu238" ao="1.0471e-05" />
<nuclide name="Pu239" ao="1.5300e-04" />
<nuclide name="Pu240" ao="6.5540e-05" />
<nuclide name="Pu241" ao="3.6032e-05" />
<nuclide name="Pu242" ao="2.0303e-05" />
<nuclide name="Am241" ao="1.1405e-05" />
<nuclide name="Am243" ao="6.1550e-06" />
<nuclide name="Np237" ao="2.1806e-05" />
<nuclide name="Mo95" ao="6.9892e-05" />
<nuclide name="Tc99" ao="6.6975e-05" />
<nuclide name="Ru101" ao="6.7875e-05" />
<nuclide name="Rh103" ao="3.5406e-05" />
<nuclide name="Ag109" ao="6.9836e-06" />
<nuclide name="Cs133" ao="7.2263e-05" />
<nuclide name="Sm147" ao="1.0106e-05" />
<nuclide name="Sm149" ao="1.9259e-07" />
<nuclide name="Sm150" ao="1.8627e-05" />
<nuclide name="Sm151" ao="8.1779e-07" />
<nuclide name="Sm152" ao="6.7637e-06" />
<nuclide name="Nd143" ao="4.5992e-05" />
<nuclide name="Nd145" ao="3.9892e-05" />
<nuclide name="Eu153" ao="6.5858e-06" />
<nuclide name="Gd155" ao="6.0862e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
</materials>

View file

@ -0,0 +1,35 @@
<?xml version="1.0"?>
<settings>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<run_mode>eigenvalue</run_mode>
<batches>1200</batches>
<inactive>200</inactive>
<particles>10000</particles>
<source>
<space>
<type>box</type>
<parameters>
-0.665 -0.665 0.
0.665 0.665 429.2
</parameters>
</space>
</source>
<mesh id="1">
<lower_left>-0.665 -0.665 0.</lower_left>
<upper_right>0.665 0.665 429.2</upper_right>
<dimension>1 1 400</dimension>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

View file

@ -0,0 +1,57 @@
<?xml version="1.0"?>
<geometry>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2, Case 2_1
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.412" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-plane" coeffs="0." boundary="vacuum" />
<surface id="4" type="z-plane" coeffs="30." />
<surface id="5" type="z-plane" coeffs="31.75" />
<surface id="6" type="z-plane" coeffs="36.75" />
<surface id="7" type="z-plane" coeffs="41.75" />
<surface id="8" type="z-plane" coeffs="51.75" />
<surface id="9" type="z-plane" coeffs="71.75" />
<surface id="10" type="z-plane" coeffs="357.45" />
<surface id="11" type="z-plane" coeffs="377.45" />
<surface id="12" type="z-plane" coeffs="387.45" />
<surface id="13" type="z-plane" coeffs="392.45" />
<surface id="14" type="z-plane" coeffs="397.45" />
<surface id="15" type="z-plane" coeffs="399.2" />
<surface id="16" type="z-plane" coeffs="429.2" boundary="vacuum" />
<surface id="20" type="x-plane" coeffs="-0.665" boundary="reflective" />
<surface id="21" type="x-plane" coeffs="0.665" boundary="reflective" />
<surface id="22" type="y-plane" coeffs="-0.665" boundary="reflective" />
<surface id="23" type="y-plane" coeffs="0.665" boundary="reflective" />
<!-- Surrounding water -->
<cell id="1" material="1" region="20 -21 22 -23 3 -4" />
<cell id="2" material="1" region="20 -21 22 -23 4 -15 2" />
<cell id="3" material="1" region="20 -21 22 -23 15 -16" />
<!-- Cladding, end plugs -->
<cell id="4" material="2" region=" -2 4 -5" />
<cell id="5" material="2" region="1 -2 5 -14" />
<cell id="6" material="2" region=" -2 14 -15" />
<!-- Fuel regions 9->1 -->
<cell id="7" material="6" region="-1 5 -6" />
<cell id="8" material="7" region="-1 6 -7" />
<cell id="9" material="8" region="-1 7 -8" />
<cell id="10" material="9" region="-1 8 -9" />
<cell id="11" material="10" region="-1 9 -10" />
<cell id="12" material="9" region="-1 10 -11" />
<cell id="13" material="8" region="-1 11 -12" />
<cell id="14" material="7" region="-1 12 -13" />
<cell id="15" material="6" region="-1 13 -14" />
</geometry>

View file

@ -0,0 +1,238 @@
<?xml version="1.0"?>
<materials>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
NOTE THE FUEL DENSITIES NEED UPDATING
-->
<!-- Water, 25 deg.C -->
<material id="1">
<density value="0.099987" units="atom/b-cm" />
<nuclide name="H1" ao="6.6658e-02" />
<nuclide name="O16" ao="3.3329e-02" />
<sab name="c_H_in_H2O" />
</material>
<!-- Zircaloy-4 -->
<material id="2">
<density value="0.043206271" units="atom/b-cm" />
<nuclide name="Cr50" ao="3.2975e-06" />
<nuclide name="Cr52" ao="6.3588e-05" />
<nuclide name="Cr53" ao="7.2104e-06" />
<nuclide name="Cr54" ao="1.7948e-06" />
<nuclide name="Fe54" ao="8.6728e-06" />
<nuclide name="Fe56" ao="1.3614e-04" />
<nuclide name="Fe57" ao="3.1442e-06" />
<nuclide name="Fe58" ao="4.1843e-07" />
<nuclide name="Zr90" ao="2.2114e-02" />
<nuclide name="Zr91" ao="4.8226e-03" />
<nuclide name="Zr92" ao="7.3714e-03" />
<nuclide name="Zr94" ao="7.4703e-03" />
<nuclide name="Zr96" ao="1.2035e-03" />
</material>
<!-- ====================== Fresh fuels =========================== -->
<!-- EU45: UO2, 4.5wt% enriched -->
<material id="3">
<density value="0.0693284852" units="atom/b-cm" />
<nuclide name="U234" ao="8.4100e-06" />
<nuclide name="U235" ao="1.0526e-03" />
<nuclide name="U236" ao="6.4752e-06" />
<nuclide name="U238" ao="2.2042e-02" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- EU40: UO2, 4.0wt% enriched -->
<material id="4">
<density value="0.0696080381" units="atom/b-cm" />
<nuclide name="U234" ao="7.5481e-06" />
<nuclide name="U235" ao="9.3949e-04" />
<nuclide name="U238" ao="2.2256e-02" />
<nuclide name="O16" ao="4.6405e-02" />
</material>
<!-- NU: UO2, Natural uranium -->
<material id="5">
<density value="0.0695822757" units="atom/b-cm" />
<nuclide name="U234" ao="1.2757e-06" />
<nuclide name="U235" ao="1.6700e-04" />
<nuclide name="U238" ao="2.3026e-02" />
<nuclide name="O16" ao="4.6388e-02" />
</material>
<!-- ===================== Burnup fuels =========================== -->
<!-- B21G, EU45, 21.570 GWD/MTU -->
<material id="6">
<density value="0.0690055" units="atom/b-cm" />
<nuclide name="U234" ao="6.4862e-06" />
<nuclide name="U235" ao="5.6758e-04" />
<nuclide name="U236" ao="9.4556e-05" />
<nuclide name="U238" ao="2.1732e-02" />
<nuclide name="Pu238" ao="1.1322e-06" />
<nuclide name="Pu239" ao="1.2591e-04" />
<nuclide name="Pu240" ao="2.6395e-05" />
<nuclide name="Pu241" ao="1.3614e-05" />
<nuclide name="Pu242" ao="2.2623e-06" />
<nuclide name="Am241" ao="4.0266e-06" />
<nuclide name="Am243" ao="2.6222e-07" />
<nuclide name="Np237" ao="6.8089e-06" />
<nuclide name="Mo95" ao="3.1530e-05" />
<nuclide name="Tc99" ao="3.0319e-05" />
<nuclide name="Ru101" ao="2.7452e-05" />
<nuclide name="Rh103" ao="1.7260e-05" />
<nuclide name="Ag109" ao="1.8879e-06" />
<nuclide name="Cs133" ao="3.3140e-05" />
<nuclide name="Sm147" ao="6.4488e-06" />
<nuclide name="Sm149" ao="1.9390e-07" />
<nuclide name="Sm150" ao="7.1174e-06" />
<nuclide name="Sm151" ao="5.7531e-07" />
<nuclide name="Sm152" ao="3.0178e-06" />
<nuclide name="Nd143" ao="2.5793e-05" />
<nuclide name="Nd145" ao="1.8633e-05" />
<nuclide name="Eu153" ao="2.0026e-06" />
<nuclide name="Gd155" ao="1.1986e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B24G, EU45, 24.023 GWD/MTU -->
<material id="7">
<density value="0.0689673" units="atom/b-cm" />
<nuclide name="U234" ao="6.2881e-06" />
<nuclide name="U235" ao="5.2562e-04" />
<nuclide name="U236" ao="1.0155e-04" />
<nuclide name="U238" ao="2.1693e-02" />
<nuclide name="Pu238" ao="1.4876e-06" />
<nuclide name="Pu239" ao="1.3161e-04" />
<nuclide name="Pu240" ao="2.9965e-05" />
<nuclide name="Pu241" ao="1.5953e-05" />
<nuclide name="Pu242" ao="3.0335e-06" />
<nuclide name="Am241" ao="4.7603e-06" />
<nuclide name="Am243" ao="3.9809e-07" />
<nuclide name="Np237" ao="7.9041e-06" />
<nuclide name="Mo95" ao="3.4781e-05" />
<nuclide name="Tc99" ao="3.3465e-05" />
<nuclide name="Ru101" ao="3.0548e-05" />
<nuclide name="Rh103" ao="1.9008e-05" />
<nuclide name="Ag109" ao="2.2230e-06" />
<nuclide name="Cs133" ao="3.6549e-05" />
<nuclide name="Sm147" ao="6.9339e-06" />
<nuclide name="Sm149" ao="1.9611e-07" />
<nuclide name="Sm150" ao="8.0472e-06" />
<nuclide name="Sm151" ao="6.0064e-07" />
<nuclide name="Sm152" ao="3.3473e-06" />
<nuclide name="Nd143" ao="2.8067e-05" />
<nuclide name="Nd145" ao="2.0504e-05" />
<nuclide name="Eu153" ao="2.3329e-06" />
<nuclide name="Gd155" ao="1.4386e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B30G, EU45, 30.580 GWD/MTU -->
<material id="8">
<density value="0.0688634" units="atom/b-cm" />
<nuclide name="U234" ao="5.7868e-06" />
<nuclide name="U235" ao="4.2455e-04" />
<nuclide name="U236" ao="1.1763e-04" />
<nuclide name="U238" ao="2.1585e-02" />
<nuclide name="Pu238" ao="2.7262e-06" />
<nuclide name="Pu239" ao="1.4249e-04" />
<nuclide name="Pu240" ao="3.9140e-05" />
<nuclide name="Pu241" ao="2.1863e-05" />
<nuclide name="Pu242" ao="5.6472e-06" />
<nuclide name="Am241" ao="6.6579e-06" />
<nuclide name="Am243" ao="9.7353e-07" />
<nuclide name="Np237" ao="1.0948e-05" />
<nuclide name="Mo95" ao="4.3130e-05" />
<nuclide name="Tc99" ao="4.1531e-05" />
<nuclide name="Ru101" ao="3.8751e-05" />
<nuclide name="Rh103" ao="2.3371e-05" />
<nuclide name="Ag109" ao="3.1774e-06" />
<nuclide name="Cs133" ao="4.5257e-05" />
<nuclide name="Sm147" ao="8.0315e-06" />
<nuclide name="Sm149" ao="1.9935e-07" />
<nuclide name="Sm150" ao="1.0496e-05" />
<nuclide name="Sm151" ao="6.6160e-07" />
<nuclide name="Sm152" ao="4.1844e-06" />
<nuclide name="Nd143" ao="3.3502e-05" />
<nuclide name="Nd145" ao="2.5263e-05" />
<nuclide name="Eu153" ao="3.2546e-06" />
<nuclide name="Gd155" ao="2.2155e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU45, 40.424 GWD/MTU -->
<material id="9">
<density value="0.0687030" units="atom/b-cm" />
<nuclide name="U234" ao="5.1152e-06" />
<nuclide name="U235" ao="3.0002e-04" />
<nuclide name="U236" ao="1.3534e-04" />
<nuclide name="U238" ao="2.1413e-02" />
<nuclide name="Pu238" ao="5.3656e-06" />
<nuclide name="Pu239" ao="1.5064e-04" />
<nuclide name="Pu240" ao="5.1484e-05" />
<nuclide name="Pu241" ao="2.9175e-05" />
<nuclide name="Pu242" ao="1.0893e-05" />
<nuclide name="Am241" ao="9.0866e-06" />
<nuclide name="Am243" ao="2.5108e-06" />
<nuclide name="Np237" ao="1.5602e-05" />
<nuclide name="Mo95" ao="5.4806e-05" />
<nuclide name="Tc99" ao="5.2746e-05" />
<nuclide name="Ru101" ao="5.0881e-05" />
<nuclide name="Rh103" ao="2.9057e-05" />
<nuclide name="Ag109" ao="4.7134e-06" />
<nuclide name="Cs133" ao="5.7263e-05" />
<nuclide name="Sm147" ao="9.2075e-06" />
<nuclide name="Sm149" ao="1.9993e-07" />
<nuclide name="Sm150" ao="1.3997e-05" />
<nuclide name="Sm151" ao="7.3765e-07" />
<nuclide name="Sm152" ao="5.3316e-06" />
<nuclide name="Nd143" ao="3.9984e-05" />
<nuclide name="Nd145" ao="3.1783e-05" />
<nuclide name="Eu153" ao="4.6705e-06" />
<nuclide name="Gd155" ao="3.6871e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU55, 54.605 GWD/MTU -->
<material id="10">
<density value="0.06845907" units="atom/b-cm" />
<nuclide name="U234" ao="4.3280e-06" />
<nuclide name="U235" ao="1.7108e-04" />
<nuclide name="U236" ao="1.4897e-04" />
<nuclide name="U238" ao="2.1142e-02" />
<nuclide name="Pu238" ao="1.0471e-05" />
<nuclide name="Pu239" ao="1.5300e-04" />
<nuclide name="Pu240" ao="6.5540e-05" />
<nuclide name="Pu241" ao="3.6032e-05" />
<nuclide name="Pu242" ao="2.0303e-05" />
<nuclide name="Am241" ao="1.1405e-05" />
<nuclide name="Am243" ao="6.1550e-06" />
<nuclide name="Np237" ao="2.1806e-05" />
<nuclide name="Mo95" ao="6.9892e-05" />
<nuclide name="Tc99" ao="6.6975e-05" />
<nuclide name="Ru101" ao="6.7875e-05" />
<nuclide name="Rh103" ao="3.5406e-05" />
<nuclide name="Ag109" ao="6.9836e-06" />
<nuclide name="Cs133" ao="7.2263e-05" />
<nuclide name="Sm147" ao="1.0106e-05" />
<nuclide name="Sm149" ao="1.9259e-07" />
<nuclide name="Sm150" ao="1.8627e-05" />
<nuclide name="Sm151" ao="8.1779e-07" />
<nuclide name="Sm152" ao="6.7637e-06" />
<nuclide name="Nd143" ao="4.5992e-05" />
<nuclide name="Nd145" ao="3.9892e-05" />
<nuclide name="Eu153" ao="6.5858e-06" />
<nuclide name="Gd155" ao="6.0862e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
</materials>

View file

@ -0,0 +1,35 @@
<?xml version="1.0"?>
<settings>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<run_mode>eigenvalue</run_mode>
<batches>1200</batches>
<inactive>200</inactive>
<particles>10000</particles>
<source>
<space>
<type>box</type>
<parameters>
-0.665 -0.665 0.
0.665 0.665 429.2
</parameters>
</space>
</source>
<mesh id="1">
<lower_left>-0.665 -0.665 0.</lower_left>
<upper_right>0.665 0.665 429.2</upper_right>
<dimension>1 1 400</dimension>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

View file

@ -0,0 +1,57 @@
<?xml version="1.0"?>
<geometry>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2, Case 2_2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.412" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-plane" coeffs="0." boundary="vacuum" />
<surface id="4" type="z-plane" coeffs="30." />
<surface id="5" type="z-plane" coeffs="31.75" />
<surface id="6" type="z-plane" coeffs="36.75" />
<surface id="7" type="z-plane" coeffs="41.75" />
<surface id="8" type="z-plane" coeffs="51.75" />
<surface id="9" type="z-plane" coeffs="71.75" />
<surface id="10" type="z-plane" coeffs="357.45" />
<surface id="11" type="z-plane" coeffs="377.45" />
<surface id="12" type="z-plane" coeffs="387.45" />
<surface id="13" type="z-plane" coeffs="392.45" />
<surface id="14" type="z-plane" coeffs="397.45" />
<surface id="15" type="z-plane" coeffs="399.2" />
<surface id="16" type="z-plane" coeffs="429.2" boundary="vacuum" />
<surface id="20" type="x-plane" coeffs="-0.665" boundary="reflective" />
<surface id="21" type="x-plane" coeffs="0.665" boundary="reflective" />
<surface id="22" type="y-plane" coeffs="-0.665" boundary="reflective" />
<surface id="23" type="y-plane" coeffs="0.665" boundary="reflective" />
<!-- Surrounding water -->
<cell id="1" material="1" region="20 -21 22 -23 3 -4" />
<cell id="2" material="1" region="20 -21 22 -23 4 -15 2" />
<cell id="3" material="1" region="20 -21 22 -23 15 -16" />
<!-- Cladding, end plugs -->
<cell id="4" material="2" region=" -2 4 -5" />
<cell id="5" material="2" region="1 -2 5 -14" />
<cell id="6" material="2" region=" -2 14 -15" />
<!-- Fuel regions 9->1 -->
<cell id="7" material="7" region="-1 5 -6" />
<cell id="8" material="8" region="-1 6 -7" />
<cell id="9" material="9" region="-1 7 -8" />
<cell id="10" material="10" region="-1 8 -9" />
<cell id="11" material="10" region="-1 9 -10" />
<cell id="12" material="9" region="-1 10 -11" />
<cell id="13" material="8" region="-1 11 -12" />
<cell id="14" material="7" region="-1 12 -13" />
<cell id="15" material="6" region="-1 13 -14" />
</geometry>

View file

@ -0,0 +1,238 @@
<?xml version="1.0"?>
<materials>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
NOTE THE FUEL DENSITIES NEED UPDATING
-->
<!-- Water, 25 deg.C -->
<material id="1">
<density value="0.099987" units="atom/b-cm" />
<nuclide name="H1" ao="6.6658e-02" />
<nuclide name="O16" ao="3.3329e-02" />
<sab name="c_H_in_H2O" />
</material>
<!-- Zircaloy-4 -->
<material id="2">
<density value="0.043206271" units="atom/b-cm" />
<nuclide name="Cr50" ao="3.2975e-06" />
<nuclide name="Cr52" ao="6.3588e-05" />
<nuclide name="Cr53" ao="7.2104e-06" />
<nuclide name="Cr54" ao="1.7948e-06" />
<nuclide name="Fe54" ao="8.6728e-06" />
<nuclide name="Fe56" ao="1.3614e-04" />
<nuclide name="Fe57" ao="3.1442e-06" />
<nuclide name="Fe58" ao="4.1843e-07" />
<nuclide name="Zr90" ao="2.2114e-02" />
<nuclide name="Zr91" ao="4.8226e-03" />
<nuclide name="Zr92" ao="7.3714e-03" />
<nuclide name="Zr94" ao="7.4703e-03" />
<nuclide name="Zr96" ao="1.2035e-03" />
</material>
<!-- ====================== Fresh fuels =========================== -->
<!-- EU45: UO2, 4.5wt% enriched -->
<material id="3">
<density value="0.0693284852" units="atom/b-cm" />
<nuclide name="U234" ao="8.4100e-06" />
<nuclide name="U235" ao="1.0526e-03" />
<nuclide name="U236" ao="6.4752e-06" />
<nuclide name="U238" ao="2.2042e-02" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- EU40: UO2, 4.0wt% enriched -->
<material id="4">
<density value="0.0696080381" units="atom/b-cm" />
<nuclide name="U234" ao="7.5481e-06" />
<nuclide name="U235" ao="9.3949e-04" />
<nuclide name="U238" ao="2.2256e-02" />
<nuclide name="O16" ao="4.6405e-02" />
</material>
<!-- NU: UO2, Natural uranium -->
<material id="5">
<density value="0.0695822757" units="atom/b-cm" />
<nuclide name="U234" ao="1.2757e-06" />
<nuclide name="U235" ao="1.6700e-04" />
<nuclide name="U238" ao="2.3026e-02" />
<nuclide name="O16" ao="4.6388e-02" />
</material>
<!-- ===================== Burnup fuels =========================== -->
<!-- B21G, EU45, 21.570 GWD/MTU -->
<material id="6">
<density value="0.0690055" units="atom/b-cm" />
<nuclide name="U234" ao="6.4862e-06" />
<nuclide name="U235" ao="5.6758e-04" />
<nuclide name="U236" ao="9.4556e-05" />
<nuclide name="U238" ao="2.1732e-02" />
<nuclide name="Pu238" ao="1.1322e-06" />
<nuclide name="Pu239" ao="1.2591e-04" />
<nuclide name="Pu240" ao="2.6395e-05" />
<nuclide name="Pu241" ao="1.3614e-05" />
<nuclide name="Pu242" ao="2.2623e-06" />
<nuclide name="Am241" ao="4.0266e-06" />
<nuclide name="Am243" ao="2.6222e-07" />
<nuclide name="Np237" ao="6.8089e-06" />
<nuclide name="Mo95" ao="3.1530e-05" />
<nuclide name="Tc99" ao="3.0319e-05" />
<nuclide name="Ru101" ao="2.7452e-05" />
<nuclide name="Rh103" ao="1.7260e-05" />
<nuclide name="Ag109" ao="1.8879e-06" />
<nuclide name="Cs133" ao="3.3140e-05" />
<nuclide name="Sm147" ao="6.4488e-06" />
<nuclide name="Sm149" ao="1.9390e-07" />
<nuclide name="Sm150" ao="7.1174e-06" />
<nuclide name="Sm151" ao="5.7531e-07" />
<nuclide name="Sm152" ao="3.0178e-06" />
<nuclide name="Nd143" ao="2.5793e-05" />
<nuclide name="Nd145" ao="1.8633e-05" />
<nuclide name="Eu153" ao="2.0026e-06" />
<nuclide name="Gd155" ao="1.1986e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B24G, EU45, 24.023 GWD/MTU -->
<material id="7">
<density value="0.0689673" units="atom/b-cm" />
<nuclide name="U234" ao="6.2881e-06" />
<nuclide name="U235" ao="5.2562e-04" />
<nuclide name="U236" ao="1.0155e-04" />
<nuclide name="U238" ao="2.1693e-02" />
<nuclide name="Pu238" ao="1.4876e-06" />
<nuclide name="Pu239" ao="1.3161e-04" />
<nuclide name="Pu240" ao="2.9965e-05" />
<nuclide name="Pu241" ao="1.5953e-05" />
<nuclide name="Pu242" ao="3.0335e-06" />
<nuclide name="Am241" ao="4.7603e-06" />
<nuclide name="Am243" ao="3.9809e-07" />
<nuclide name="Np237" ao="7.9041e-06" />
<nuclide name="Mo95" ao="3.4781e-05" />
<nuclide name="Tc99" ao="3.3465e-05" />
<nuclide name="Ru101" ao="3.0548e-05" />
<nuclide name="Rh103" ao="1.9008e-05" />
<nuclide name="Ag109" ao="2.2230e-06" />
<nuclide name="Cs133" ao="3.6549e-05" />
<nuclide name="Sm147" ao="6.9339e-06" />
<nuclide name="Sm149" ao="1.9611e-07" />
<nuclide name="Sm150" ao="8.0472e-06" />
<nuclide name="Sm151" ao="6.0064e-07" />
<nuclide name="Sm152" ao="3.3473e-06" />
<nuclide name="Nd143" ao="2.8067e-05" />
<nuclide name="Nd145" ao="2.0504e-05" />
<nuclide name="Eu153" ao="2.3329e-06" />
<nuclide name="Gd155" ao="1.4386e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B30G, EU45, 30.580 GWD/MTU -->
<material id="8">
<density value="0.0688634" units="atom/b-cm" />
<nuclide name="U234" ao="5.7868e-06" />
<nuclide name="U235" ao="4.2455e-04" />
<nuclide name="U236" ao="1.1763e-04" />
<nuclide name="U238" ao="2.1585e-02" />
<nuclide name="Pu238" ao="2.7262e-06" />
<nuclide name="Pu239" ao="1.4249e-04" />
<nuclide name="Pu240" ao="3.9140e-05" />
<nuclide name="Pu241" ao="2.1863e-05" />
<nuclide name="Pu242" ao="5.6472e-06" />
<nuclide name="Am241" ao="6.6579e-06" />
<nuclide name="Am243" ao="9.7353e-07" />
<nuclide name="Np237" ao="1.0948e-05" />
<nuclide name="Mo95" ao="4.3130e-05" />
<nuclide name="Tc99" ao="4.1531e-05" />
<nuclide name="Ru101" ao="3.8751e-05" />
<nuclide name="Rh103" ao="2.3371e-05" />
<nuclide name="Ag109" ao="3.1774e-06" />
<nuclide name="Cs133" ao="4.5257e-05" />
<nuclide name="Sm147" ao="8.0315e-06" />
<nuclide name="Sm149" ao="1.9935e-07" />
<nuclide name="Sm150" ao="1.0496e-05" />
<nuclide name="Sm151" ao="6.6160e-07" />
<nuclide name="Sm152" ao="4.1844e-06" />
<nuclide name="Nd143" ao="3.3502e-05" />
<nuclide name="Nd145" ao="2.5263e-05" />
<nuclide name="Eu153" ao="3.2546e-06" />
<nuclide name="Gd155" ao="2.2155e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU45, 40.424 GWD/MTU -->
<material id="9">
<density value="0.0687030" units="atom/b-cm" />
<nuclide name="U234" ao="5.1152e-06" />
<nuclide name="U235" ao="3.0002e-04" />
<nuclide name="U236" ao="1.3534e-04" />
<nuclide name="U238" ao="2.1413e-02" />
<nuclide name="Pu238" ao="5.3656e-06" />
<nuclide name="Pu239" ao="1.5064e-04" />
<nuclide name="Pu240" ao="5.1484e-05" />
<nuclide name="Pu241" ao="2.9175e-05" />
<nuclide name="Pu242" ao="1.0893e-05" />
<nuclide name="Am241" ao="9.0866e-06" />
<nuclide name="Am243" ao="2.5108e-06" />
<nuclide name="Np237" ao="1.5602e-05" />
<nuclide name="Mo95" ao="5.4806e-05" />
<nuclide name="Tc99" ao="5.2746e-05" />
<nuclide name="Ru101" ao="5.0881e-05" />
<nuclide name="Rh103" ao="2.9057e-05" />
<nuclide name="Ag109" ao="4.7134e-06" />
<nuclide name="Cs133" ao="5.7263e-05" />
<nuclide name="Sm147" ao="9.2075e-06" />
<nuclide name="Sm149" ao="1.9993e-07" />
<nuclide name="Sm150" ao="1.3997e-05" />
<nuclide name="Sm151" ao="7.3765e-07" />
<nuclide name="Sm152" ao="5.3316e-06" />
<nuclide name="Nd143" ao="3.9984e-05" />
<nuclide name="Nd145" ao="3.1783e-05" />
<nuclide name="Eu153" ao="4.6705e-06" />
<nuclide name="Gd155" ao="3.6871e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU55, 54.605 GWD/MTU -->
<material id="10">
<density value="0.06845907" units="atom/b-cm" />
<nuclide name="U234" ao="4.3280e-06" />
<nuclide name="U235" ao="1.7108e-04" />
<nuclide name="U236" ao="1.4897e-04" />
<nuclide name="U238" ao="2.1142e-02" />
<nuclide name="Pu238" ao="1.0471e-05" />
<nuclide name="Pu239" ao="1.5300e-04" />
<nuclide name="Pu240" ao="6.5540e-05" />
<nuclide name="Pu241" ao="3.6032e-05" />
<nuclide name="Pu242" ao="2.0303e-05" />
<nuclide name="Am241" ao="1.1405e-05" />
<nuclide name="Am243" ao="6.1550e-06" />
<nuclide name="Np237" ao="2.1806e-05" />
<nuclide name="Mo95" ao="6.9892e-05" />
<nuclide name="Tc99" ao="6.6975e-05" />
<nuclide name="Ru101" ao="6.7875e-05" />
<nuclide name="Rh103" ao="3.5406e-05" />
<nuclide name="Ag109" ao="6.9836e-06" />
<nuclide name="Cs133" ao="7.2263e-05" />
<nuclide name="Sm147" ao="1.0106e-05" />
<nuclide name="Sm149" ao="1.9259e-07" />
<nuclide name="Sm150" ao="1.8627e-05" />
<nuclide name="Sm151" ao="8.1779e-07" />
<nuclide name="Sm152" ao="6.7637e-06" />
<nuclide name="Nd143" ao="4.5992e-05" />
<nuclide name="Nd145" ao="3.9892e-05" />
<nuclide name="Eu153" ao="6.5858e-06" />
<nuclide name="Gd155" ao="6.0862e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
</materials>

View file

@ -0,0 +1,35 @@
<?xml version="1.0"?>
<settings>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<run_mode>eigenvalue</run_mode>
<batches>1200</batches>
<inactive>200</inactive>
<particles>10000</particles>
<source>
<space>
<type>box</type>
<parameters>
-0.665 -0.665 0.
0.665 0.665 429.2
</parameters>
</space>
</source>
<mesh id="1">
<lower_left>-0.665 -0.665 0.</lower_left>
<upper_right>0.665 0.665 429.2</upper_right>
<dimension>1 1 400</dimension>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

View file

@ -0,0 +1,57 @@
<?xml version="1.0"?>
<geometry>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2, Case 2_3
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.412" />
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.475" />
<surface id="3" type="z-plane" coeffs="0." boundary="vacuum" />
<surface id="4" type="z-plane" coeffs="30." />
<surface id="5" type="z-plane" coeffs="31.75" />
<surface id="6" type="z-plane" coeffs="36.75" />
<surface id="7" type="z-plane" coeffs="41.75" />
<surface id="8" type="z-plane" coeffs="51.75" />
<surface id="9" type="z-plane" coeffs="71.75" />
<surface id="10" type="z-plane" coeffs="357.45" />
<surface id="11" type="z-plane" coeffs="377.45" />
<surface id="12" type="z-plane" coeffs="387.45" />
<surface id="13" type="z-plane" coeffs="392.45" />
<surface id="14" type="z-plane" coeffs="397.45" />
<surface id="15" type="z-plane" coeffs="399.2" />
<surface id="16" type="z-plane" coeffs="429.2" boundary="vacuum" />
<surface id="20" type="x-plane" coeffs="-0.665" boundary="reflective" />
<surface id="21" type="x-plane" coeffs="0.665" boundary="reflective" />
<surface id="22" type="y-plane" coeffs="-0.665" boundary="reflective" />
<surface id="23" type="y-plane" coeffs="0.665" boundary="reflective" />
<!-- Surrounding water -->
<cell id="1" material="1" region="20 -21 22 -23 3 -4" />
<cell id="2" material="1" region="20 -21 22 -23 4 -15 2" />
<cell id="3" material="1" region="20 -21 22 -23 15 -16" />
<!-- Cladding, end plugs -->
<cell id="4" material="2" region=" -2 4 -5" />
<cell id="5" material="2" region="1 -2 5 -14" />
<cell id="6" material="2" region=" -2 14 -15" />
<!-- Fuel regions 9->1 -->
<cell id="7" material="7" region="-1 5 -6" />
<cell id="8" material="8" region="-1 6 -7" />
<cell id="9" material="8" region="-1 7 -8" />
<cell id="10" material="9" region="-1 8 -9" />
<cell id="11" material="10" region="-1 9 -10" />
<cell id="12" material="9" region="-1 10 -11" />
<cell id="13" material="8" region="-1 11 -12" />
<cell id="14" material="7" region="-1 12 -13" />
<cell id="15" material="6" region="-1 13 -14" />
</geometry>

View file

@ -0,0 +1,238 @@
<?xml version="1.0"?>
<materials>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
NOTE THE FUEL DENSITIES NEED UPDATING
-->
<!-- Water, 25 deg.C -->
<material id="1">
<density value="0.099987" units="atom/b-cm" />
<nuclide name="H1" ao="6.6658e-02" />
<nuclide name="O16" ao="3.3329e-02" />
<sab name="c_H_in_H2O" />
</material>
<!-- Zircaloy-4 -->
<material id="2">
<density value="0.043206271" units="atom/b-cm" />
<nuclide name="Cr50" ao="3.2975e-06" />
<nuclide name="Cr52" ao="6.3588e-05" />
<nuclide name="Cr53" ao="7.2104e-06" />
<nuclide name="Cr54" ao="1.7948e-06" />
<nuclide name="Fe54" ao="8.6728e-06" />
<nuclide name="Fe56" ao="1.3614e-04" />
<nuclide name="Fe57" ao="3.1442e-06" />
<nuclide name="Fe58" ao="4.1843e-07" />
<nuclide name="Zr90" ao="2.2114e-02" />
<nuclide name="Zr91" ao="4.8226e-03" />
<nuclide name="Zr92" ao="7.3714e-03" />
<nuclide name="Zr94" ao="7.4703e-03" />
<nuclide name="Zr96" ao="1.2035e-03" />
</material>
<!-- ====================== Fresh fuels =========================== -->
<!-- EU45: UO2, 4.5wt% enriched -->
<material id="3">
<density value="0.0693284852" units="atom/b-cm" />
<nuclide name="U234" ao="8.4100e-06" />
<nuclide name="U235" ao="1.0526e-03" />
<nuclide name="U236" ao="6.4752e-06" />
<nuclide name="U238" ao="2.2042e-02" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- EU40: UO2, 4.0wt% enriched -->
<material id="4">
<density value="0.0696080381" units="atom/b-cm" />
<nuclide name="U234" ao="7.5481e-06" />
<nuclide name="U235" ao="9.3949e-04" />
<nuclide name="U238" ao="2.2256e-02" />
<nuclide name="O16" ao="4.6405e-02" />
</material>
<!-- NU: UO2, Natural uranium -->
<material id="5">
<density value="0.0695822757" units="atom/b-cm" />
<nuclide name="U234" ao="1.2757e-06" />
<nuclide name="U235" ao="1.6700e-04" />
<nuclide name="U238" ao="2.3026e-02" />
<nuclide name="O16" ao="4.6388e-02" />
</material>
<!-- ===================== Burnup fuels =========================== -->
<!-- B21G, EU45, 21.570 GWD/MTU -->
<material id="6">
<density value="0.0690055" units="atom/b-cm" />
<nuclide name="U234" ao="6.4862e-06" />
<nuclide name="U235" ao="5.6758e-04" />
<nuclide name="U236" ao="9.4556e-05" />
<nuclide name="U238" ao="2.1732e-02" />
<nuclide name="Pu238" ao="1.1322e-06" />
<nuclide name="Pu239" ao="1.2591e-04" />
<nuclide name="Pu240" ao="2.6395e-05" />
<nuclide name="Pu241" ao="1.3614e-05" />
<nuclide name="Pu242" ao="2.2623e-06" />
<nuclide name="Am241" ao="4.0266e-06" />
<nuclide name="Am243" ao="2.6222e-07" />
<nuclide name="Np237" ao="6.8089e-06" />
<nuclide name="Mo95" ao="3.1530e-05" />
<nuclide name="Tc99" ao="3.0319e-05" />
<nuclide name="Ru101" ao="2.7452e-05" />
<nuclide name="Rh103" ao="1.7260e-05" />
<nuclide name="Ag109" ao="1.8879e-06" />
<nuclide name="Cs133" ao="3.3140e-05" />
<nuclide name="Sm147" ao="6.4488e-06" />
<nuclide name="Sm149" ao="1.9390e-07" />
<nuclide name="Sm150" ao="7.1174e-06" />
<nuclide name="Sm151" ao="5.7531e-07" />
<nuclide name="Sm152" ao="3.0178e-06" />
<nuclide name="Nd143" ao="2.5793e-05" />
<nuclide name="Nd145" ao="1.8633e-05" />
<nuclide name="Eu153" ao="2.0026e-06" />
<nuclide name="Gd155" ao="1.1986e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B24G, EU45, 24.023 GWD/MTU -->
<material id="7">
<density value="0.0689673" units="atom/b-cm" />
<nuclide name="U234" ao="6.2881e-06" />
<nuclide name="U235" ao="5.2562e-04" />
<nuclide name="U236" ao="1.0155e-04" />
<nuclide name="U238" ao="2.1693e-02" />
<nuclide name="Pu238" ao="1.4876e-06" />
<nuclide name="Pu239" ao="1.3161e-04" />
<nuclide name="Pu240" ao="2.9965e-05" />
<nuclide name="Pu241" ao="1.5953e-05" />
<nuclide name="Pu242" ao="3.0335e-06" />
<nuclide name="Am241" ao="4.7603e-06" />
<nuclide name="Am243" ao="3.9809e-07" />
<nuclide name="Np237" ao="7.9041e-06" />
<nuclide name="Mo95" ao="3.4781e-05" />
<nuclide name="Tc99" ao="3.3465e-05" />
<nuclide name="Ru101" ao="3.0548e-05" />
<nuclide name="Rh103" ao="1.9008e-05" />
<nuclide name="Ag109" ao="2.2230e-06" />
<nuclide name="Cs133" ao="3.6549e-05" />
<nuclide name="Sm147" ao="6.9339e-06" />
<nuclide name="Sm149" ao="1.9611e-07" />
<nuclide name="Sm150" ao="8.0472e-06" />
<nuclide name="Sm151" ao="6.0064e-07" />
<nuclide name="Sm152" ao="3.3473e-06" />
<nuclide name="Nd143" ao="2.8067e-05" />
<nuclide name="Nd145" ao="2.0504e-05" />
<nuclide name="Eu153" ao="2.3329e-06" />
<nuclide name="Gd155" ao="1.4386e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B30G, EU45, 30.580 GWD/MTU -->
<material id="8">
<density value="0.0688634" units="atom/b-cm" />
<nuclide name="U234" ao="5.7868e-06" />
<nuclide name="U235" ao="4.2455e-04" />
<nuclide name="U236" ao="1.1763e-04" />
<nuclide name="U238" ao="2.1585e-02" />
<nuclide name="Pu238" ao="2.7262e-06" />
<nuclide name="Pu239" ao="1.4249e-04" />
<nuclide name="Pu240" ao="3.9140e-05" />
<nuclide name="Pu241" ao="2.1863e-05" />
<nuclide name="Pu242" ao="5.6472e-06" />
<nuclide name="Am241" ao="6.6579e-06" />
<nuclide name="Am243" ao="9.7353e-07" />
<nuclide name="Np237" ao="1.0948e-05" />
<nuclide name="Mo95" ao="4.3130e-05" />
<nuclide name="Tc99" ao="4.1531e-05" />
<nuclide name="Ru101" ao="3.8751e-05" />
<nuclide name="Rh103" ao="2.3371e-05" />
<nuclide name="Ag109" ao="3.1774e-06" />
<nuclide name="Cs133" ao="4.5257e-05" />
<nuclide name="Sm147" ao="8.0315e-06" />
<nuclide name="Sm149" ao="1.9935e-07" />
<nuclide name="Sm150" ao="1.0496e-05" />
<nuclide name="Sm151" ao="6.6160e-07" />
<nuclide name="Sm152" ao="4.1844e-06" />
<nuclide name="Nd143" ao="3.3502e-05" />
<nuclide name="Nd145" ao="2.5263e-05" />
<nuclide name="Eu153" ao="3.2546e-06" />
<nuclide name="Gd155" ao="2.2155e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU45, 40.424 GWD/MTU -->
<material id="9">
<density value="0.0687030" units="atom/b-cm" />
<nuclide name="U234" ao="5.1152e-06" />
<nuclide name="U235" ao="3.0002e-04" />
<nuclide name="U236" ao="1.3534e-04" />
<nuclide name="U238" ao="2.1413e-02" />
<nuclide name="Pu238" ao="5.3656e-06" />
<nuclide name="Pu239" ao="1.5064e-04" />
<nuclide name="Pu240" ao="5.1484e-05" />
<nuclide name="Pu241" ao="2.9175e-05" />
<nuclide name="Pu242" ao="1.0893e-05" />
<nuclide name="Am241" ao="9.0866e-06" />
<nuclide name="Am243" ao="2.5108e-06" />
<nuclide name="Np237" ao="1.5602e-05" />
<nuclide name="Mo95" ao="5.4806e-05" />
<nuclide name="Tc99" ao="5.2746e-05" />
<nuclide name="Ru101" ao="5.0881e-05" />
<nuclide name="Rh103" ao="2.9057e-05" />
<nuclide name="Ag109" ao="4.7134e-06" />
<nuclide name="Cs133" ao="5.7263e-05" />
<nuclide name="Sm147" ao="9.2075e-06" />
<nuclide name="Sm149" ao="1.9993e-07" />
<nuclide name="Sm150" ao="1.3997e-05" />
<nuclide name="Sm151" ao="7.3765e-07" />
<nuclide name="Sm152" ao="5.3316e-06" />
<nuclide name="Nd143" ao="3.9984e-05" />
<nuclide name="Nd145" ao="3.1783e-05" />
<nuclide name="Eu153" ao="4.6705e-06" />
<nuclide name="Gd155" ao="3.6871e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
<!-- B40G, EU55, 54.605 GWD/MTU -->
<material id="10">
<density value="0.06845907" units="atom/b-cm" />
<nuclide name="U234" ao="4.3280e-06" />
<nuclide name="U235" ao="1.7108e-04" />
<nuclide name="U236" ao="1.4897e-04" />
<nuclide name="U238" ao="2.1142e-02" />
<nuclide name="Pu238" ao="1.0471e-05" />
<nuclide name="Pu239" ao="1.5300e-04" />
<nuclide name="Pu240" ao="6.5540e-05" />
<nuclide name="Pu241" ao="3.6032e-05" />
<nuclide name="Pu242" ao="2.0303e-05" />
<nuclide name="Am241" ao="1.1405e-05" />
<nuclide name="Am243" ao="6.1550e-06" />
<nuclide name="Np237" ao="2.1806e-05" />
<nuclide name="Mo95" ao="6.9892e-05" />
<nuclide name="Tc99" ao="6.6975e-05" />
<nuclide name="Ru101" ao="6.7875e-05" />
<nuclide name="Rh103" ao="3.5406e-05" />
<nuclide name="Ag109" ao="6.9836e-06" />
<nuclide name="Cs133" ao="7.2263e-05" />
<nuclide name="Sm147" ao="1.0106e-05" />
<nuclide name="Sm149" ao="1.9259e-07" />
<nuclide name="Sm150" ao="1.8627e-05" />
<nuclide name="Sm151" ao="8.1779e-07" />
<nuclide name="Sm152" ao="6.7637e-06" />
<nuclide name="Nd143" ao="4.5992e-05" />
<nuclide name="Nd145" ao="3.9892e-05" />
<nuclide name="Eu153" ao="6.5858e-06" />
<nuclide name="Gd155" ao="6.0862e-07" />
<nuclide name="O16" ao="4.6219e-02" />
</material>
</materials>

View file

@ -0,0 +1,35 @@
<?xml version="1.0"?>
<settings>
<!--
==============================================================
Description: Infinite array of fuel pins
Case: OECD/NEA Source Convergence Benchmark 2
Written by: Ruaridh Macdonald
Date: 3/5/2012
==============================================================
-->
<run_mode>eigenvalue</run_mode>
<batches>1200</batches>
<inactive>200</inactive>
<particles>10000</particles>
<source>
<space>
<type>box</type>
<parameters>
-0.665 -0.665 0.
0.665 0.665 429.2
</parameters>
</space>
</source>
<mesh id="1">
<lower_left>-0.665 -0.665 0.</lower_left>
<upper_right>0.665 0.665 429.2</upper_right>
<dimension>1 1 400</dimension>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

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