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

This commit is contained in:
Adam Parler 2023-10-19 01:27:08 -07:00
commit b3d17759b8
132 changed files with 27211 additions and 0 deletions

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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
====================================================
-->
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 -->
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<nuclide name="U-235" xs="71c" wo="0.0185105302348" />
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<nuclide name="O-16" xs="71c" wo="0.118546179294" />
</material>
<!-- Helium for gap -->
<material id="2">
<density value="1.00000e-4" units="atom/b-cm" />
<nuclide name="He-4" xs="71c" ao="1.0" />
</material>
<!-- Zircaloy 4 -->
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<density value="6.55" units="g/cc" />
<nuclide name="O-16" xs="71c" wo="0.00125" />
<nuclide name="Nb-93" xs="71c" wo="0.01" />
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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>
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</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
====================================================
-->
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/home/ahmedk/Desktop/NuclearCodes/Cross_section_data/nndc/293.6K/cross_sections_mcnp6.1.xml</cross_sections>
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============================> TALLY 1 <============================
Cell 1
Total Material
Flux 48.1251 +/- 1.04779E-02
============================> TALLY 2 <============================
Cell 1
Total Material
Nu-Fission Rate 1.23740 +/- 6.41088E-04
============================> TALLY 3 <============================
Cell 1
Total Material
Delayed-Nu-Fission Rate 8.78552E-03 +/- 4.24096E-06
============================> TALLY 4 <============================
Cell 1
Total Material
Fission Rate 0.503212 +/- 2.62902E-04
============================> TALLY 5 <============================
Cell 1
Total Material
Absorption Rate 1.00134 +/- 4.25218E-04
============================> TALLY 6 <============================
Cell 1
Total Material
Scattering Rate 33.8552 +/- 9.30306E-03
============================> TALLY 7 <============================
Cell 1
Total Material
Total Reaction Rate 34.8566 +/- 9.65666E-03
============================> TALLY 8 <============================
Delayed Group 1
Total Material
Delayed-Nu-Fission Rate 2.53152E-04 +/- 1.33191E-07
Delayed Group 2
Total Material
Delayed-Nu-Fission Rate 1.39554E-03 +/- 6.98258E-07
Delayed Group 3
Total Material
Delayed-Nu-Fission Rate 1.37422E-03 +/- 6.79073E-07
Delayed Group 4
Total Material
Delayed-Nu-Fission Rate 4.02822E-03 +/- 1.94805E-06
Delayed Group 5
Total Material
Delayed-Nu-Fission Rate 1.30113E-03 +/- 5.88791E-07
Delayed Group 6
Total Material
Delayed-Nu-Fission Rate 4.33259E-04 +/- 2.02954E-07

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<?xml version="1.0"?>
<tallies>
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AP1000/PWR 2.1/summary.h5 Normal file

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============================> TALLY 1 <============================
Cell 1
Total Material
Flux 48.1251 +/- 1.04779E-02
============================> TALLY 2 <============================
Cell 1
Total Material
Nu-Fission Rate 1.23740 +/- 6.41088E-04
============================> TALLY 3 <============================
Cell 1
Total Material
Delayed-Nu-Fission Rate 8.78552E-03 +/- 4.24096E-06
============================> TALLY 4 <============================
Cell 1
Total Material
Fission Rate 0.503212 +/- 2.62902E-04
============================> TALLY 5 <============================
Cell 1
Total Material
Absorption Rate 1.00134 +/- 4.25218E-04
============================> TALLY 6 <============================
Cell 1
Total Material
Scattering Rate 33.8552 +/- 9.30306E-03
============================> TALLY 7 <============================
Cell 1
Total Material
Total Reaction Rate 34.8566 +/- 9.65666E-03
============================> TALLY 8 <============================
Delayed Group 1
Total Material
Delayed-Nu-Fission Rate 2.53152E-04 +/- 1.33191E-07
Delayed Group 2
Total Material
Delayed-Nu-Fission Rate 1.39554E-03 +/- 6.98258E-07
Delayed Group 3
Total Material
Delayed-Nu-Fission Rate 1.37422E-03 +/- 6.79073E-07
Delayed Group 4
Total Material
Delayed-Nu-Fission Rate 4.02822E-03 +/- 1.94805E-06
Delayed Group 5
Total Material
Delayed-Nu-Fission Rate 1.30113E-03 +/- 5.88791E-07
Delayed Group 6
Total Material
Delayed-Nu-Fission Rate 4.33259E-04 +/- 2.02954E-07

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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
====================================================
-->
<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="U-235" xs="71c" wo="0.0229176" />
<nuclide name="U-238" xs="71c" wo="0.858529" />
<nuclide name="O-16" xs="71c" wo="0.11855276" />
</material>
<!-- Helium for gap -->
<material id="2">
<density value="1.00000e-4" units="atom/b-cm" />
<nuclide name="He-4" xs="71c" ao="1.0" />
</material>
<!-- Zircaloy 4 -->
<material id="3">
<density value="6.55" units="g/cc" />
<nuclide name="O-16" xs="71c" wo="0.00125" />
<nuclide name="Nb-93" xs="71c" wo="0.01" />
<nuclide name="Sn-112" xs="71c" wo="0.000097" />
<nuclide name="Sn-114" xs="71c" wo="0.000066" />
<nuclide name="Sn-115" xs="71c" wo="0.000034" />
<nuclide name="Sn-116" xs="71c" wo="0.001454" />
<nuclide name="Sn-117" xs="71c" wo="0.000768" />
<nuclide name="Sn-118" xs="71c" wo="0.002422 " />
<nuclide name="Sn-119" xs="71c" wo="0.000859" />
<nuclide name="Sn-120" xs="71c" wo="0.003258" />
<nuclide name="Sn-122" xs="71c" wo="0.000463" />
<nuclide name="Sn-124" xs="71c" wo="0.000579" />
<nuclide name="Fe-54" xs="71c" wo="0.00005845" />
<nuclide name="Fe-56" xs="71c" wo="0.00091754" />
<nuclide name="Fe-57" xs="71c" wo="0.00002119" />
<nuclide name="Fe-58" xs="71c" wo="0.00000282" />
<nuclide name="Zr-90" xs="71c" wo="0.503052375" />
<nuclide name="Zr-91" xs="71c" wo="0.10970355" />
<nuclide name="Zr-92" xs="71c" wo="0.167684125" />
<nuclide name="Zr-94" xs="71c" wo="0.16993295" />
<nuclide name="Zr-96" xs="71c" wo="0.027377" />
</material>
<!-- Water -->
<material id="4">
<density value="0.73" units="g/cc" />
<nuclide name="H-1" xs="71c" ao="2.0" />
<nuclide name="O-16" xs="71c" ao="1.0" />
<sab name="lwtr" xs="04t" />
</material>
<!-- Guide Tube -->
<material id="5">
<density value="7.92" units="g/cc" />
<nuclide name="Ni-58" xs="71c" wo="0.06467315" />
<nuclide name="Ni-60" xs="71c" wo="0.02492135" />
<nuclide name="Ni-61" xs="71c" wo="0.001082905" />
<nuclide name="Ni-62" xs="71c" wo="0.00345287" />
<nuclide name="Ni-64" xs="71c" wo="0.000879225" />
<nuclide name="Fe-54" xs="71c" wo="0.04062275" />
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<nuclide name="Fe-57" xs="71c" wo="0.01472705" />
<nuclide name="Fe-58" xs="71c" wo="0.0019599" />
<nuclide name="Mn-55" xs="71c" wo="0.020" />
<nuclide name="Cr-50" xs="71c" wo="0.0082555" />
<nuclide name="Cr-52" xs="71c" wo="0.1591991" />
<nuclide name="Cr-53" xs="71c" wo="0.0180519" />
<nuclide name="Cr-54" xs="71c" wo="0.0044935" />
</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
====================================================
-->
<cross_sections>
/home/ahmedk/Desktop/xdata/cross_sections.xml
</cross_sections>
<eigenvalue>
<batches>600</batches>
<inactive>50</inactive>
<particles>10000</particles>
</eigenvalue>
<source>
<space>
<type>box</type>
<parameters>
-10.659 -10.659 -182.9
10.659 10.659 182.9
</parameters>
</space>
</source>
</settings>

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@ -0,0 +1,47 @@
<?xml version="1.0"?>
<tallies>
<tally id="1">
<filter type="cell" bins="1" />
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="1" />
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="1" />
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="1" />
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="1" />
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="1" />
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

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AP1000/PWR 2.6/summary.h5 Normal file

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============================> TALLY 1 <============================
Cell 1
Total Material
Flux 46.5121 +/- 1.02981E-02
============================> TALLY 2 <============================
Cell 1
Total Material
Nu-Fission Rate 1.29545 +/- 6.77359E-04
============================> TALLY 3 <============================
Cell 1
Total Material
Delayed-Nu-Fission Rate 9.15835E-03 +/- 4.46167E-06
============================> TALLY 4 <============================
Cell 1
Total Material
Fission Rate 0.526995 +/- 2.77877E-04
============================> TALLY 5 <============================
Cell 1
Total Material
Absorption Rate 1.00188 +/- 4.34804E-04
============================> TALLY 6 <============================
Cell 1
Total Material
Scattering Rate 31.8304 +/- 8.61290E-03
============================> TALLY 7 <============================
Cell 1
Total Material
Total Reaction Rate 32.8323 +/- 8.96590E-03
============================> TALLY 8 <============================
Delayed Group 1
Total Material
Delayed-Nu-Fission Rate 2.65238E-04 +/- 1.40824E-07
Delayed Group 2
Total Material
Delayed-Nu-Fission Rate 1.45796E-03 +/- 7.36344E-07
Delayed Group 3
Total Material
Delayed-Nu-Fission Rate 1.43462E-03 +/- 7.15562E-07
Delayed Group 4
Total Material
Delayed-Nu-Fission Rate 4.19965E-03 +/- 2.04970E-06
Delayed Group 5
Total Material
Delayed-Nu-Fission Rate 1.35014E-03 +/- 6.15735E-07
Delayed Group 6
Total Material
Delayed-Nu-Fission Rate 4.50745E-04 +/- 2.12997E-07

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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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<materials>
<!--
====================================================
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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<!--
====================================================
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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<!--
====================================================
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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BIN
AP1000/PWR 3.10/summary.h5 Normal file

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============================> TALLY 1 <============================
Cell 1
Total Material
Flux 45.2682 +/- 9.83436E-03
============================> TALLY 2 <============================
Cell 1
Total Material
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Total Material
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Total Material
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============================> TALLY 5 <============================
Cell 1
Total Material
Absorption Rate 1.00157 +/- 4.39105E-04
============================> TALLY 6 <============================
Cell 1
Total Material
Scattering Rate 30.2793 +/- 7.79164E-03
============================> TALLY 7 <============================
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Total Reaction Rate 31.2809 +/- 8.14277E-03
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Total Material
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Delayed Group 2
Total Material
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Total Material
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Total Material
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Delayed Group 5
Total Material
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Delayed Group 6
Total Material
Delayed-Nu-Fission Rate 4.63176E-04 +/- 2.21685E-07

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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
====================================================
-->
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<?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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@ -0,0 +1,20 @@
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<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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@ -0,0 +1,35 @@
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<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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BIN
ARC700/CANDU 2.1/summary.h5 Normal file

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@ -0,0 +1,84 @@
============================> TALLY 1 <============================
Cell 93
Total Material
Flux 163.424 +/- 5.28121E-02
Cell 87
Total Material
Flux 0.0 +/- 0.0
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Total Material
Nu-Fission Rate 1.26106 +/- 6.40821E-04
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Total Material
Nu-Fission Rate 0.0 +/- 0.0
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Total Material
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Total Material
Delayed-Nu-Fission Rate 0.0 +/- 0.0
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Total Material
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Total Material
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Total Material
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Total Material
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Total Material
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Total Material
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Total Material
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Delayed Group 2
Total Material
Delayed-Nu-Fission Rate 1.40181E-03 +/- 6.95039E-07
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Total Material
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Delayed Group 4
Total Material
Delayed-Nu-Fission Rate 3.98570E-03 +/- 1.92860E-06
Delayed Group 5
Total Material
Delayed-Nu-Fission Rate 1.24331E-03 +/- 5.70304E-07
Delayed Group 6
Total Material
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File diff suppressed because one or more lines are too long

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@ -0,0 +1,217 @@
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====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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<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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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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@ -0,0 +1,35 @@
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<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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@ -0,0 +1,47 @@
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BIN
ARC700/CANDU 2.6/summary.h5 Normal file

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@ -0,0 +1,84 @@
============================> TALLY 1 <============================
Cell 93
Total Material
Flux 157.157 +/- 4.94838E-02
Cell 87
Total Material
Flux 0.0 +/- 0.0
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Cell 93
Total Material
Nu-Fission Rate 1.32360 +/- 6.54682E-04
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Total Material
Nu-Fission Rate 0.0 +/- 0.0
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Cell 93
Total Material
Delayed-Nu-Fission Rate 9.08830E-03 +/- 4.28404E-06
Cell 87
Total Material
Delayed-Nu-Fission Rate 0.0 +/- 0.0
============================> TALLY 4 <============================
Cell 93
Total Material
Fission Rate 0.540215 +/- 2.68485E-04
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Total Material
Fission Rate 0.0 +/- 0.0
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Total Material
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Total Material
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Total Material
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Total Material
Scattering Rate 0.0 +/- 0.0
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Total Material
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Total Material
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Delayed Group 1
Total Material
Delayed-Nu-Fission Rate 2.72592E-04 +/- 1.35988E-07
Delayed Group 2
Total Material
Delayed-Nu-Fission Rate 1.46917E-03 +/- 7.09705E-07
Delayed Group 3
Total Material
Delayed-Nu-Fission Rate 1.43818E-03 +/- 6.88963E-07
Delayed Group 4
Total Material
Delayed-Nu-Fission Rate 4.17091E-03 +/- 1.96860E-06
Delayed Group 5
Total Material
Delayed-Nu-Fission Rate 1.29643E-03 +/- 5.81586E-07
Delayed Group 6
Total Material
Delayed-Nu-Fission Rate 4.41012E-04 +/- 2.03381E-07

File diff suppressed because one or more lines are too long

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@ -0,0 +1,217 @@
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<!--
====================================================
Description: ACR1000 Assembly 43 Fuel pins
Case: Problem (43 fuel pins)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
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<?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
====================================================
-->
<default_xs>71c</default_xs>
<material id="11">
<density value="9.82" units="g/cc" />
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<nuclide name="U-238" xs="73c" wo="96.9" />
<nuclide name="O-16" xs="73c" wo="13.4529" />
</material>
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<nuclide name="Dy-163" xs="72c" wo="1.861" />
<nuclide name="Dy-164" xs="72c" wo="2.1317" />
</material>
<!-- Zircaloy 4 -->
<material id="2">
<density value="7.48" units="g/cc" />
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<nuclide name="Cr-50" xs="71c" wo="0.004345" />
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</materials>

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@ -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>

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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
====================================================
-->
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/home/ahmedk/Desktop/xdata/cross_sections1.xml
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</parameters>
</space>
</source>
</settings>

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<?xml version="1.0"?>
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<scores>delayed-nu-fission</scores>
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<tally id="4">
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</tally>
</tallies>

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ARC700/CANDU 3.1/summary.h5 Normal file

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============================> TALLY 1 <============================
Cell 93
Total Material
Flux 152.257 +/- 4.58838E-02
Cell 87
Total Material
Flux 0.0 +/- 0.0
============================> TALLY 2 <============================
Cell 93
Total Material
Nu-Fission Rate 1.36990 +/- 7.02126E-04
Cell 87
Total Material
Nu-Fission Rate 0.0 +/- 0.0
============================> TALLY 3 <============================
Cell 93
Total Material
Delayed-Nu-Fission Rate 9.38572E-03 +/- 4.57395E-06
Cell 87
Total Material
Delayed-Nu-Fission Rate 0.0 +/- 0.0
============================> TALLY 4 <============================
Cell 93
Total Material
Fission Rate 0.559204 +/- 2.88087E-04
Cell 87
Total Material
Fission Rate 0.0 +/- 0.0
============================> TALLY 5 <============================
Cell 93
Total Material
Absorption Rate 1.00287 +/- 4.35912E-04
Cell 87
Total Material
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============================> TALLY 6 <============================
Cell 93
Total Material
Scattering Rate 54.6965 +/- 1.73526E-02
Cell 87
Total Material
Scattering Rate 0.0 +/- 0.0
============================> TALLY 7 <============================
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Total Material
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Cell 87
Total Material
Total Reaction Rate 0.0 +/- 0.0
============================> TALLY 8 <============================
Delayed Group 1
Total Material
Delayed-Nu-Fission Rate 2.82242E-04 +/- 1.45970E-07
Delayed Group 2
Total Material
Delayed-Nu-Fission Rate 1.51899E-03 +/- 7.59665E-07
Delayed Group 3
Total Material
Delayed-Nu-Fission Rate 1.48638E-03 +/- 7.36856E-07
Delayed Group 4
Total Material
Delayed-Nu-Fission Rate 4.30767E-03 +/- 2.10212E-06
Delayed Group 5
Total Material
Delayed-Nu-Fission Rate 1.33549E-03 +/- 6.16825E-07
Delayed Group 6
Total Material
Delayed-Nu-Fission Rate 4.54956E-04 +/- 2.16568E-07

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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
====================================================
-->
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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
====================================================
-->
<materials>
<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="U-235" xs="80c" wo="0.0185105302348" />
<nuclide name="U-238" xs="80c" wo="0.862943290471" />
<nuclide name="O-16" xs="80c" wo="0.118546179294" />
</material>
<!-- 3.6% UO2 + 5% Gd2O3 -->
<material id="5">
<density value="10.547" units="g/cc" />
<nuclide name="U-235" xs="80c" wo="0.0292792" />
<nuclide name="U-238" xs="80c" wo="0.7940422" />
<nuclide name="O-16" xs="80c" wo="0.1194922" />
<nuclide name="Gd-157" xs="80c" wo="0.0571954 " />
</material>
<!-- Cladding material alloy Э110 -->
<material id="2">
<density value="6.4516" units="g/cc" />
<nuclide name="Nb-93" xs="80c" wo="0.0100" />
<nuclide name="Hf-174" xs="80c" wo="0.00000048" />
<nuclide name="Hf-176" xs="80c" wo="0.00001578" />
<nuclide name="Hf-177" xs="80c" wo="0.0000558" />
<nuclide name="Hf-178" xs="80c" wo="0.00008184" />
<nuclide name="Hf-179" xs="80c" wo="0.00004086" />
<nuclide name="Hf-180" xs="80c" wo="0.00010524" />
<nuclide name="Zr-90" xs="80c" wo="0.50920065" />
<nuclide name="Zr-91" xs="80c" wo="0.11104434" />
<nuclide name="Zr-92" xs="80c" wo="0.16973355" />
<nuclide name="Zr-94" xs="80c" wo="0.17200986" />
<nuclide name="Zr-96" xs="80c" wo="0.0277116" />
</material>
<!-- Water -->
<material id="3">
<density value="0.716" units="g/cc" />
<nuclide name="H-1" xs="80c" wo="0.06312" />
<nuclide name="O-16" xs="80c" wo="0.13539" />
<nuclide name="B-11" xs="80c" wo="0.80149" />
</material>
<!-- Guide Tube alloy Э635 -->
<material id="4">
<density value="6.55" units="g/cc" />
<nuclide name="Nb-93" xs="80c" wo="0.0100" />
<nuclide name="Sn-112" xs="80c" wo="0.0001261" />
<nuclide name="Sn-114" xs="80c" wo="0.0000858" />
<nuclide name="Sn-115" xs="80c" wo="0.0000442" />
<nuclide name="Sn-116" xs="80c" wo="0.0018902" />
<nuclide name="Sn-117" xs="80c" wo="0.0009984" />
<nuclide name="Sn-118" xs="80c" wo="0.0031486" />
<nuclide name="Sn-119" xs="80c" wo="0.0011167" />
<nuclide name="Sn-120" xs="80c" wo="0.0042354" />
<nuclide name="Sn-122" xs="80c" wo="0.0006019" />
<nuclide name="Sn-124" xs="80c" wo="0.0007527" />
<nuclide name="Fe-54" xs="80c" wo="0.00017535" />
<nuclide name="Fe-56" xs="80c" wo="0.00275262" />
<nuclide name="Fe-57" xs="80c" wo="0.00006357" />
<nuclide name="Fe-58" xs="80c" wo="0.00000846" />
<nuclide name="Zr-90" xs="80c" wo="0.50662815" />
<nuclide name="Zr-91" xs="80c" wo="0.11048334" />
<nuclide name="Zr-92" xs="80c" wo="0.16887605" />
<nuclide name="Zr-94" xs="80c" wo="0.17114086" />
<nuclide name="Zr-96" 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
====================================================
-->
<cross_sections>
/home/ahmedk/Desktop/xdata/cross_sections1.xml
</cross_sections>
<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>
<tally id="1">
<filter type="cell" bins="1" />
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="1" />
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="1" />
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="1" />
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="1" />
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="1" />
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

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============================> TALLY 1 <============================
Cell 1
Total Material
Flux 64.9018 +/- 1.33778E-02
============================> TALLY 2 <============================
Cell 1
Total Material
Nu-Fission Rate 0.997313 +/- 5.50758E-04
============================> TALLY 3 <============================
Cell 1
Total Material
Delayed-Nu-Fission Rate 7.33525E-03 +/- 3.68047E-06
============================> TALLY 4 <============================
Cell 1
Total Material
Fission Rate 0.404201 +/- 2.25497E-04
============================> TALLY 5 <============================
Cell 1
Total Material
Absorption Rate 1.00166 +/- 4.10541E-04
============================> TALLY 6 <============================
Cell 1
Total Material
Scattering Rate 28.7426 +/- 5.85780E-03
============================> TALLY 7 <============================
Cell 1
Total Material
Total Reaction Rate 29.7443 +/- 6.10826E-03
============================> TALLY 8 <============================
Delayed Group 1
Total Material
Delayed-Nu-Fission Rate 2.25891E-04 +/- 1.25118E-07
Delayed Group 2
Total Material
Delayed-Nu-Fission Rate 1.22589E-03 +/- 6.50769E-07
Delayed Group 3
Total Material
Delayed-Nu-Fission Rate 1.20457E-03 +/- 6.25374E-07
Delayed Group 4
Total Material
Delayed-Nu-Fission Rate 2.83474E-03 +/- 1.42311E-06
Delayed Group 5
Total Material
Delayed-Nu-Fission Rate 1.30311E-03 +/- 6.16517E-07
Delayed Group 6
Total Material
Delayed-Nu-Fission Rate 5.41041E-04 +/- 2.56891E-07

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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>
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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'?>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<materials>
<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="U-235" xs="80c" wo="0.0229176280555" />
<nuclide name="U-238" xs="80c" wo="0.858529604849" />
<nuclide name="O-16" xs="80c" wo="0.118552767096" />
</material>
<!-- 3.6% UO2 + 5% Gd2O3 -->
<material id="5">
<density value="10.547" units="g/cc" />
<nuclide name="U-235" xs="80c" wo="0.0292792" />
<nuclide name="U-238" xs="80c" wo="0.7940422" />
<nuclide name="O-16" xs="80c" wo="0.1194922" />
<nuclide name="Gd-157" xs="80c" wo="0.0571954 " />
</material>
<!-- Cladding material alloy Э110 -->
<material id="2">
<density value="6.4516" units="g/cc" />
<nuclide name="Nb-93" xs="80c" wo="0.0100" />
<nuclide name="Hf-174" xs="80c" wo="0.00000048" />
<nuclide name="Hf-176" xs="80c" wo="0.00001578" />
<nuclide name="Hf-177" xs="80c" wo="0.0000558" />
<nuclide name="Hf-178" xs="80c" wo="0.00008184" />
<nuclide name="Hf-179" xs="80c" wo="0.00004086" />
<nuclide name="Hf-180" xs="80c" wo="0.00010524" />
<nuclide name="Zr-90" xs="80c" wo="0.50920065" />
<nuclide name="Zr-91" xs="80c" wo="0.11104434" />
<nuclide name="Zr-92" xs="80c" wo="0.16973355" />
<nuclide name="Zr-94" xs="80c" wo="0.17200986" />
<nuclide name="Zr-96" xs="80c" wo="0.0277116" />
</material>
<!-- Water -->
<material id="3">
<density value="0.716" units="g/cc" />
<nuclide name="H-1" xs="80c" wo="0.06312" />
<nuclide name="O-16" xs="80c" wo="0.13539" />
<nuclide name="B-11" xs="80c" wo="0.80149" />
</material>
<!-- Guide Tube alloy Э635 -->
<material id="4">
<density value="6.55" units="g/cc" />
<nuclide name="Nb-93" xs="80c" wo="0.0100" />
<nuclide name="Sn-112" xs="80c" wo="0.0001261" />
<nuclide name="Sn-114" xs="80c" wo="0.0000858" />
<nuclide name="Sn-115" xs="80c" wo="0.0000442" />
<nuclide name="Sn-116" xs="80c" wo="0.0018902" />
<nuclide name="Sn-117" xs="80c" wo="0.0009984" />
<nuclide name="Sn-118" xs="80c" wo="0.0031486" />
<nuclide name="Sn-119" xs="80c" wo="0.0011167" />
<nuclide name="Sn-120" xs="80c" wo="0.0042354" />
<nuclide name="Sn-122" xs="80c" wo="0.0006019" />
<nuclide name="Sn-124" xs="80c" wo="0.0007527" />
<nuclide name="Fe-54" xs="80c" wo="0.00017535" />
<nuclide name="Fe-56" xs="80c" wo="0.00275262" />
<nuclide name="Fe-57" xs="80c" wo="0.00006357" />
<nuclide name="Fe-58" xs="80c" wo="0.00000846" />
<nuclide name="Zr-90" xs="80c" wo="0.50662815" />
<nuclide name="Zr-91" xs="80c" wo="0.11048334" />
<nuclide name="Zr-92" xs="80c" wo="0.16887605" />
<nuclide name="Zr-94" xs="80c" wo="0.17114086" />
<nuclide name="Zr-96" 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
====================================================
-->
<cross_sections>
/home/ahmedk/Desktop/xdata/cross_sections1.xml
</cross_sections>
<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>
<tally id="1">
<filter type="cell" bins="1" />
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="1" />
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="1" />
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="1" />
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="1" />
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="1" />
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

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============================> TALLY 1 <============================
Cell 1
Total Material
Flux 63.7640 +/- 1.32958E-02
============================> TALLY 2 <============================
Cell 1
Total Material
Nu-Fission Rate 1.05453 +/- 5.91572E-04
============================> TALLY 3 <============================
Cell 1
Total Material
Delayed-Nu-Fission Rate 7.70342E-03 +/- 3.90170E-06
============================> TALLY 4 <============================
Cell 1
Total Material
Fission Rate 0.427644 +/- 2.42306E-04
============================> TALLY 5 <============================
Cell 1
Total Material
Absorption Rate 1.00180 +/- 4.29561E-04
============================> TALLY 6 <============================
Cell 1
Total Material
Scattering Rate 28.0157 +/- 5.83095E-03
============================> TALLY 7 <============================
Cell 1
Total Material
Total Reaction Rate 29.0175 +/- 6.09326E-03
============================> TALLY 8 <============================
Delayed Group 1
Total Material
Delayed-Nu-Fission Rate 2.38933E-04 +/- 1.34371E-07
Delayed Group 2
Total Material
Delayed-Nu-Fission Rate 1.29291E-03 +/- 6.96071E-07
Delayed Group 3
Total Material
Delayed-Nu-Fission Rate 1.26839E-03 +/- 6.66953E-07
Delayed Group 4
Total Material
Delayed-Nu-Fission Rate 2.97715E-03 +/- 1.50882E-06
Delayed Group 5
Total Material
Delayed-Nu-Fission Rate 1.36080E-03 +/- 6.41808E-07
Delayed Group 6
Total Material
Delayed-Nu-Fission Rate 5.65231E-04 +/- 2.67859E-07

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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>
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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'?>
<!--
====================================================
Description: VVER 1000 (Russian PWR Design)
Case: Problem 3 (Hexagonal PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<materials>
<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="U-235" xs="80c" wo="0.03221694" />
<nuclide name="U-238" xs="80c" wo="0.84921578" />
<nuclide name="O-16" xs="80c" wo="0.11856726" />
</material>
<!-- 3.6% UO2 + 5% Gd2O3 -->
<material id="5">
<density value="10.547" units="g/cc" />
<nuclide name="U-235" xs="80c" wo="0.0292792" />
<nuclide name="U-238" xs="80c" wo="0.7940422" />
<nuclide name="O-16" xs="80c" wo="0.1194922" />
<nuclide name="Gd-157" xs="80c" wo="0.0571954 " />
</material>
<!-- Cladding material alloy Э110 -->
<material id="2">
<density value="6.4516" units="g/cc" />
<nuclide name="Nb-93" xs="80c" wo="0.0100" />
<nuclide name="Hf-174" xs="80c" wo="0.00000048" />
<nuclide name="Hf-176" xs="80c" wo="0.00001578" />
<nuclide name="Hf-177" xs="80c" wo="0.0000558" />
<nuclide name="Hf-178" xs="80c" wo="0.00008184" />
<nuclide name="Hf-179" xs="80c" wo="0.00004086" />
<nuclide name="Hf-180" xs="80c" wo="0.00010524" />
<nuclide name="Zr-90" xs="80c" wo="0.50920065" />
<nuclide name="Zr-91" xs="80c" wo="0.11104434" />
<nuclide name="Zr-92" xs="80c" wo="0.16973355" />
<nuclide name="Zr-94" xs="80c" wo="0.17200986" />
<nuclide name="Zr-96" xs="80c" wo="0.0277116" />
</material>
<!-- Water -->
<material id="3">
<density value="0.716" units="g/cc" />
<nuclide name="H-1" xs="80c" wo="0.06312" />
<nuclide name="O-16" xs="80c" wo="0.13539" />
<nuclide name="B-11" xs="80c" wo="0.80149" />
</material>
<!-- Guide Tube alloy Э635 -->
<material id="4">
<density value="6.55" units="g/cc" />
<nuclide name="Nb-93" xs="80c" wo="0.0100" />
<nuclide name="Sn-112" xs="80c" wo="0.0001261" />
<nuclide name="Sn-114" xs="80c" wo="0.0000858" />
<nuclide name="Sn-115" xs="80c" wo="0.0000442" />
<nuclide name="Sn-116" xs="80c" wo="0.0018902" />
<nuclide name="Sn-117" xs="80c" wo="0.0009984" />
<nuclide name="Sn-118" xs="80c" wo="0.0031486" />
<nuclide name="Sn-119" xs="80c" wo="0.0011167" />
<nuclide name="Sn-120" xs="80c" wo="0.0042354" />
<nuclide name="Sn-122" xs="80c" wo="0.0006019" />
<nuclide name="Sn-124" xs="80c" wo="0.0007527" />
<nuclide name="Fe-54" xs="80c" wo="0.00017535" />
<nuclide name="Fe-56" xs="80c" wo="0.00275262" />
<nuclide name="Fe-57" xs="80c" wo="0.00006357" />
<nuclide name="Fe-58" xs="80c" wo="0.00000846" />
<nuclide name="Zr-90" xs="80c" wo="0.50662815" />
<nuclide name="Zr-91" xs="80c" wo="0.11048334" />
<nuclide name="Zr-92" xs="80c" wo="0.16887605" />
<nuclide name="Zr-94" xs="80c" wo="0.17114086" />
<nuclide name="Zr-96" 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
====================================================
-->
<cross_sections>
/home/ahmedk/Desktop/xdata/cross_sections1.xml
</cross_sections>
<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 +1,46 @@
<?xml version="1.0"?>
<tallies>
<tally id="1">
<filter type="cell" bins="1" />
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="1" />
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="1" />
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="1" />
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="1" />
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="1" />
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

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BIN
VVER/VVER 3.6/summary.h5 Normal file

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63
VVER/VVER 3.6/tallies.out Normal file
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============================> TALLY 1 <============================
Cell 1
Total Material
Flux 61.9896 +/- 1.28230E-02
============================> TALLY 2 <============================
Cell 1
Total Material
Nu-Fission Rate 1.13900 +/- 6.24803E-04
============================> TALLY 3 <============================
Cell 1
Total Material
Delayed-Nu-Fission Rate 8.24555E-03 +/- 4.13592E-06
============================> TALLY 4 <============================
Cell 1
Total Material
Fission Rate 0.462219 +/- 2.55841E-04
============================> TALLY 5 <============================
Cell 1
Total Material
Absorption Rate 1.00181 +/- 4.24571E-04
============================> TALLY 6 <============================
Cell 1
Total Material
Scattering Rate 26.8902 +/- 5.57261E-03
============================> TALLY 7 <============================
Cell 1
Total Material
Total Reaction Rate 27.8920 +/- 5.83435E-03
============================> TALLY 8 <============================
Delayed Group 1
Total Material
Delayed-Nu-Fission Rate 2.58189E-04 +/- 1.41929E-07
Delayed Group 2
Total Material
Delayed-Nu-Fission Rate 1.39177E-03 +/- 7.36533E-07
Delayed Group 3
Total Material
Delayed-Nu-Fission Rate 1.36245E-03 +/- 7.06298E-07
Delayed Group 4
Total Material
Delayed-Nu-Fission Rate 3.18686E-03 +/- 1.59938E-06
Delayed Group 5
Total Material
Delayed-Nu-Fission Rate 1.44552E-03 +/- 6.80326E-07
Delayed Group 6
Total Material
Delayed-Nu-Fission Rate 6.00761E-04 +/- 2.83970E-07

81
chain_simple.xml Normal file
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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>

1556
depletion.ipynb Normal file

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411
hexagonal-lattice.ipynb Normal file

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389
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

656
mc-performance/openmc/build.py Executable file
View file

@ -0,0 +1,656 @@
#!/usr/bin/env python
from argparse import ArgumentParser
import numpy as np
import openmc
parser = ArgumentParser()
parser.add_argument('-s', '--size', action='store', default='small',
help='Size of nuclide inventory (small or large)')
args = parser.parse_args()
# Define materials
fuel = openmc.Material(name='Fuel', material_id=1)
fuel.set_density('g/cm3', 10.062)
fuel.add_nuclide("U234", 4.9476e-6)
fuel.add_nuclide("U235", 4.8218e-4)
fuel.add_nuclide("U236", 9.0402e-5)
fuel.add_nuclide("U238", 2.1504e-2)
fuel.add_nuclide("Np237", 7.3733e-6)
fuel.add_nuclide("Pu238", 1.5148e-6)
fuel.add_nuclide("Pu239", 1.3955e-4)
fuel.add_nuclide("Pu240", 3.4405e-5)
fuel.add_nuclide("Pu241", 2.1439e-5)
fuel.add_nuclide("Pu242", 3.7422e-6)
fuel.add_nuclide("Am241", 4.5041e-7)
fuel.add_nuclide("Am242_m1", 9.2301e-9)
fuel.add_nuclide("Am243", 4.7878e-7)
fuel.add_nuclide("Cm242", 1.0485e-7)
fuel.add_nuclide("Cm243", 1.4268e-9)
fuel.add_nuclide("Cm244", 8.8756e-8)
fuel.add_nuclide("Cm245", 3.5285e-9)
fuel.add_nuclide("Mo95", 2.6497e-5)
fuel.add_nuclide("Tc99", 3.2772e-5)
fuel.add_nuclide("Ru101", 3.0742e-5)
fuel.add_nuclide("Ru103", 2.3505e-6)
fuel.add_nuclide("Ag109", 2.0009e-6)
fuel.add_nuclide("Xe135", 1.0801e-8)
fuel.add_nuclide("Cs133", 3.4612e-5)
fuel.add_nuclide("Nd143", 2.6078e-5)
fuel.add_nuclide("Nd145", 1.9898e-5)
fuel.add_nuclide("Sm147", 1.6128e-6)
fuel.add_nuclide("Sm149", 1.1627e-7)
fuel.add_nuclide("Sm150", 7.1727e-6)
fuel.add_nuclide("Sm151", 5.4947e-7)
fuel.add_nuclide("Sm152", 3.0221e-6)
fuel.add_nuclide("Eu153", 2.6209e-6)
fuel.add_nuclide("Gd155", 1.5369e-9)
fuel.add_nuclide("O16", 4.5737e-2)
# For H-M large, add all minor actinides and fission products
if args.size == 'large':
# fission products from all actinides
fuel.add_nuclide('Cu65', 1.0e-12)
fuel.add_nuclide('Zn66', 1.0e-12)
fuel.add_nuclide('Zn67', 1.0e-12)
fuel.add_nuclide('Zn68', 1.0e-12)
fuel.add_nuclide('Zn70', 1.0e-12)
fuel.add_nuclide('Ga69', 1.0e-12)
fuel.add_nuclide('Ga71', 1.0e-12)
fuel.add_nuclide('Ge70', 1.0e-12)
fuel.add_nuclide('Ge72', 1.0e-12)
fuel.add_nuclide('Ge73', 1.0e-12)
fuel.add_nuclide('Ge74', 1.0e-12)
fuel.add_nuclide('Ge76', 1.0e-12)
fuel.add_nuclide('As74', 1.0e-12)
fuel.add_nuclide('As75', 1.0e-12)
fuel.add_nuclide('Se74', 1.0e-12)
fuel.add_nuclide('Se76', 1.0e-12)
fuel.add_nuclide('Se77', 1.0e-12)
fuel.add_nuclide('Se78', 1.0e-12)
fuel.add_nuclide('Se79', 1.0e-12)
fuel.add_nuclide('Se80', 1.0e-12)
fuel.add_nuclide('Se82', 1.0e-12)
fuel.add_nuclide('Br79', 1.0e-12)
fuel.add_nuclide('Br81', 1.0e-12)
fuel.add_nuclide('Kr78', 1.0e-12)
fuel.add_nuclide('Kr80', 1.0e-12)
fuel.add_nuclide('Kr82', 1.0e-12)
fuel.add_nuclide('Kr83', 1.0e-12)
fuel.add_nuclide('Kr84', 1.0e-12)
fuel.add_nuclide('Kr85', 1.0e-12)
fuel.add_nuclide('Kr86', 1.0e-12)
fuel.add_nuclide('Rb85', 1.0e-12)
fuel.add_nuclide('Rb86', 1.0e-12)
fuel.add_nuclide('Rb87', 1.0e-12)
fuel.add_nuclide('Sr84', 1.0e-12)
fuel.add_nuclide('Sr86', 1.0e-12)
fuel.add_nuclide('Sr87', 1.0e-12)
fuel.add_nuclide('Sr88', 1.0e-12)
fuel.add_nuclide('Sr89', 1.0e-12)
fuel.add_nuclide('Sr90', 1.0e-12)
fuel.add_nuclide('Y89', 1.0e-12)
fuel.add_nuclide('Y90', 1.0e-12)
fuel.add_nuclide('Y91', 1.0e-12)
fuel.add_nuclide('Zr90', 1.0e-12)
fuel.add_nuclide('Zr91', 1.0e-12)
fuel.add_nuclide('Zr92', 1.0e-12)
fuel.add_nuclide('Zr93', 1.0e-12)
fuel.add_nuclide('Zr94', 1.0e-12)
fuel.add_nuclide('Zr95', 1.0e-12)
fuel.add_nuclide('Zr96', 1.0e-12)
fuel.add_nuclide('Nb93', 1.0e-12)
fuel.add_nuclide('Nb94', 1.0e-12)
fuel.add_nuclide('Nb95', 1.0e-12)
fuel.add_nuclide('Mo92', 1.0e-12)
fuel.add_nuclide('Mo94', 1.0e-12)
fuel.add_nuclide('Mo96', 1.0e-12)
fuel.add_nuclide('Mo97', 1.0e-12)
fuel.add_nuclide('Mo98', 1.0e-12)
fuel.add_nuclide('Mo99', 1.0e-12)
fuel.add_nuclide('Mo100', 1.0e-12)
fuel.add_nuclide('Ru96', 1.0e-12)
fuel.add_nuclide('Ru98', 1.0e-12)
fuel.add_nuclide('Ru99', 1.0e-12)
fuel.add_nuclide('Ru100', 1.0e-12)
fuel.add_nuclide('Ru102', 1.0e-12)
fuel.add_nuclide('Ru104', 1.0e-12)
fuel.add_nuclide('Ru105', 1.0e-12)
fuel.add_nuclide('Ru106', 1.0e-12)
fuel.add_nuclide('Rh103', 1.0e-12)
fuel.add_nuclide('Rh105', 1.0e-12)
fuel.add_nuclide('Pd102', 1.0e-12)
fuel.add_nuclide('Pd104', 1.0e-12)
fuel.add_nuclide('Pd105', 1.0e-12)
fuel.add_nuclide('Pd106', 1.0e-12)
fuel.add_nuclide('Pd107', 1.0e-12)
fuel.add_nuclide('Pd108', 1.0e-12)
fuel.add_nuclide('Pd110', 1.0e-12)
fuel.add_nuclide('Ag107', 1.0e-12)
fuel.add_nuclide('Ag110_m1', 1.0e-12)
fuel.add_nuclide('Ag111', 1.0e-12)
fuel.add_nuclide('Cd106', 1.0e-12)
fuel.add_nuclide('Cd108', 1.0e-12)
fuel.add_nuclide('Cd110', 1.0e-12)
fuel.add_nuclide('Cd111', 1.0e-12)
fuel.add_nuclide('Cd112', 1.0e-12)
fuel.add_nuclide('Cd113', 1.0e-12)
fuel.add_nuclide('Cd114', 1.0e-12)
fuel.add_nuclide('Cd115_m1', 1.0e-12)
fuel.add_nuclide('Cd116', 1.0e-12)
fuel.add_nuclide('In113', 1.0e-12)
fuel.add_nuclide('In115', 1.0e-12)
fuel.add_nuclide('Sn112', 1.0e-12)
fuel.add_nuclide('Sn113', 1.0e-12)
fuel.add_nuclide('Sn114', 1.0e-12)
fuel.add_nuclide('Sn115', 1.0e-12)
fuel.add_nuclide('Sn116', 1.0e-12)
fuel.add_nuclide('Sn117', 1.0e-12)
fuel.add_nuclide('Sn118', 1.0e-12)
fuel.add_nuclide('Sn119', 1.0e-12)
fuel.add_nuclide('Sn120', 1.0e-12)
fuel.add_nuclide('Sn122', 1.0e-12)
fuel.add_nuclide('Sn123', 1.0e-12)
fuel.add_nuclide('Sn124', 1.0e-12)
fuel.add_nuclide('Sn125', 1.0e-12)
fuel.add_nuclide('Sn126', 1.0e-12)
fuel.add_nuclide('Sb121', 1.0e-12)
fuel.add_nuclide('Sb123', 1.0e-12)
fuel.add_nuclide('Sb124', 1.0e-12)
fuel.add_nuclide('Sb125', 1.0e-12)
fuel.add_nuclide('Sb126', 1.0e-12)
fuel.add_nuclide('Te120', 1.0e-12)
fuel.add_nuclide('Te122', 1.0e-12)
fuel.add_nuclide('Te123', 1.0e-12)
fuel.add_nuclide('Te124', 1.0e-12)
fuel.add_nuclide('Te125', 1.0e-12)
fuel.add_nuclide('Te126', 1.0e-12)
fuel.add_nuclide('Te127_m1', 1.0e-12)
fuel.add_nuclide('Te128', 1.0e-12)
fuel.add_nuclide('Te129_m1', 1.0e-12)
fuel.add_nuclide('Te130', 1.0e-12)
fuel.add_nuclide('Te132', 1.0e-12)
fuel.add_nuclide('I127', 1.0e-12)
fuel.add_nuclide('I129', 1.0e-12)
fuel.add_nuclide('I130', 1.0e-12)
fuel.add_nuclide('I131', 1.0e-12)
fuel.add_nuclide('I135', 1.0e-12)
fuel.add_nuclide('Xe124', 1.0e-12)
fuel.add_nuclide('Xe126', 1.0e-12)
fuel.add_nuclide('Xe128', 1.0e-12)
fuel.add_nuclide('Xe129', 1.0e-12)
fuel.add_nuclide('Xe130', 1.0e-12)
fuel.add_nuclide('Xe131', 1.0e-12)
fuel.add_nuclide('Xe132', 1.0e-12)
fuel.add_nuclide('Xe133', 1.0e-12)
fuel.add_nuclide('Xe134', 1.0e-12)
fuel.add_nuclide('Xe136', 1.0e-12)
fuel.add_nuclide('Cs134', 1.0e-12)
fuel.add_nuclide('Cs135', 1.0e-12)
fuel.add_nuclide('Cs136', 1.0e-12)
fuel.add_nuclide('Cs137', 1.0e-12)
fuel.add_nuclide('Ba132', 1.0e-12)
fuel.add_nuclide('Ba133', 1.0e-12)
fuel.add_nuclide('Ba134', 1.0e-12)
fuel.add_nuclide('Ba135', 1.0e-12)
fuel.add_nuclide('Ba136', 1.0e-12)
fuel.add_nuclide('Ba137', 1.0e-12)
fuel.add_nuclide('Ba138', 1.0e-12)
fuel.add_nuclide('Ba140', 1.0e-12)
fuel.add_nuclide('La138', 1.0e-12)
fuel.add_nuclide('La139', 1.0e-12)
fuel.add_nuclide('La140', 1.0e-12)
fuel.add_nuclide('Ce138', 1.0e-12)
fuel.add_nuclide('Ce139', 1.0e-12)
fuel.add_nuclide('Ce140', 1.0e-12)
fuel.add_nuclide('Ce141', 1.0e-12)
fuel.add_nuclide('Ce142', 1.0e-12)
fuel.add_nuclide('Ce143', 1.0e-12)
fuel.add_nuclide('Ce144', 1.0e-12)
fuel.add_nuclide('Pr141', 1.0e-12)
fuel.add_nuclide('Pr142', 1.0e-12)
fuel.add_nuclide('Pr143', 1.0e-12)
fuel.add_nuclide('Nd142', 1.0e-12)
fuel.add_nuclide('Nd144', 1.0e-12)
fuel.add_nuclide('Nd146', 1.0e-12)
fuel.add_nuclide('Nd147', 1.0e-12)
fuel.add_nuclide('Nd148', 1.0e-12)
fuel.add_nuclide('Nd150', 1.0e-12)
fuel.add_nuclide('Pm147', 1.0e-12)
fuel.add_nuclide('Pm148', 1.0e-12)
fuel.add_nuclide('Pm148_m1', 1.0e-12)
fuel.add_nuclide('Pm149', 1.0e-12)
fuel.add_nuclide('Pm151', 1.0e-12)
fuel.add_nuclide('Sm144', 1.0e-12)
fuel.add_nuclide('Sm148', 1.0e-12)
fuel.add_nuclide('Sm153', 1.0e-12)
fuel.add_nuclide('Sm154', 1.0e-12)
fuel.add_nuclide('Eu151', 1.0e-12)
fuel.add_nuclide('Eu152', 1.0e-12)
fuel.add_nuclide('Eu154', 1.0e-12)
fuel.add_nuclide('Eu155', 1.0e-12)
fuel.add_nuclide('Eu156', 1.0e-12)
fuel.add_nuclide('Eu157', 1.0e-12)
fuel.add_nuclide('Gd152', 1.0e-12)
fuel.add_nuclide('Gd153', 1.0e-12)
fuel.add_nuclide('Gd154', 1.0e-12)
fuel.add_nuclide('Gd156', 1.0e-12)
fuel.add_nuclide('Gd157', 1.0e-12)
fuel.add_nuclide('Gd158', 1.0e-12)
fuel.add_nuclide('Gd160', 1.0e-12)
fuel.add_nuclide('Tb159', 1.0e-12)
fuel.add_nuclide('Tb160', 1.0e-12)
fuel.add_nuclide('Dy156', 1.0e-12)
fuel.add_nuclide('Dy158', 1.0e-12)
fuel.add_nuclide('Dy160', 1.0e-12)
fuel.add_nuclide('Dy161', 1.0e-12)
fuel.add_nuclide('Dy162', 1.0e-12)
fuel.add_nuclide('Dy163', 1.0e-12)
fuel.add_nuclide('Dy164', 1.0e-12)
fuel.add_nuclide('Ho165', 1.0e-12)
fuel.add_nuclide('Ho166_m1', 1.0e-12)
fuel.add_nuclide('Er162', 1.0e-12)
fuel.add_nuclide('Er164', 1.0e-12)
fuel.add_nuclide('Er166', 1.0e-12)
fuel.add_nuclide('Er167', 1.0e-12)
fuel.add_nuclide('Er168', 1.0e-12)
fuel.add_nuclide('Er170', 1.0e-12)
fuel.add_nuclide('Tm168', 1.0e-12)
fuel.add_nuclide('Tm169', 1.0e-12)
fuel.add_nuclide('Tm170', 1.0e-12)
# minor actinides
fuel.add_nuclide('U233', 1.0e-12)
fuel.add_nuclide('U237', 1.0e-12)
fuel.add_nuclide('Np238', 1.0e-12)
fuel.add_nuclide('Cm246', 1.0e-12)
# other reaction products from (n,p), (n,a), etc.
fuel.add_nuclide('H1', 1.0e-12)
fuel.add_nuclide('H2', 1.0e-12)
fuel.add_nuclide('H3', 1.0e-12)
fuel.add_nuclide('He3', 1.0e-12)
fuel.add_nuclide('He4', 1.0e-12)
clad = openmc.Material(name='Cladding', material_id=2)
clad.set_density('g/cm3', 5.77)
clad.add_element("Zr", 1.0)
cold_water = openmc.Material(name='Cold borated water', material_id=3)
cold_water.set_density('atom/b-cm', 0.07416)
cold_water.add_nuclide("H1", 2.0)
cold_water.add_nuclide("O16", 1.0)
cold_water.add_nuclide("B10", 6.490e-4)
cold_water.add_nuclide("B11", 2.689e-3)
cold_water.add_s_alpha_beta('c_H_in_H2O')
hot_water = openmc.Material(name='Hot borated water', material_id=4)
hot_water.set_density('atom/b-cm', 0.06614)
hot_water.add_nuclide("H1", 2.0)
hot_water.add_nuclide("O16", 1.0)
hot_water.add_nuclide("B10", 6.490e-4)
hot_water.add_nuclide("B11", 2.689e-3)
hot_water.add_s_alpha_beta('c_H_in_H2O')
rpv_steel = openmc.Material(name='Reactor pressure vessel steel',
material_id=5)
rpv_steel.set_density('g/cm3', 7.9)
rpv_steel.add_nuclide("Fe54", 0.05437098, 'wo')
rpv_steel.add_nuclide("Fe56", 0.88500663, 'wo')
rpv_steel.add_nuclide("Fe57", 0.0208008, 'wo')
rpv_steel.add_nuclide("Fe58", 0.00282159, 'wo')
rpv_steel.add_nuclide("Ni58", 0.0067198, 'wo')
rpv_steel.add_nuclide("Ni60", 0.0026776, 'wo')
rpv_steel.add_nuclide("Ni61", 0.0001183, 'wo')
rpv_steel.add_nuclide("Ni62", 0.0003835, 'wo')
rpv_steel.add_nuclide("Ni64", 0.0001008, 'wo')
rpv_steel.add_nuclide("Mn55", 0.01, 'wo')
rpv_steel.add_nuclide("Mo92", 0.000849, 'wo')
rpv_steel.add_nuclide("Mo94", 0.0005418, 'wo')
rpv_steel.add_nuclide("Mo95", 0.0009438, 'wo')
rpv_steel.add_nuclide("Mo96", 0.0010002, 'wo')
rpv_steel.add_nuclide("Mo97", 0.0005796, 'wo')
rpv_steel.add_nuclide("Mo98", 0.0014814, 'wo')
rpv_steel.add_nuclide("Mo100", 0.0006042, 'wo')
rpv_steel.add_nuclide("Si28", 0.00367464, 'wo')
rpv_steel.add_nuclide("Si29", 0.00019336, 'wo')
rpv_steel.add_nuclide("Si30", 0.000132, 'wo')
rpv_steel.add_nuclide("Cr50", 0.00010435, 'wo')
rpv_steel.add_nuclide("Cr52", 0.002092475, 'wo')
rpv_steel.add_nuclide("Cr53", 0.00024185, 'wo')
rpv_steel.add_nuclide("Cr54", 6.1325e-05, 'wo')
rpv_steel.add_nuclide("C0", 0.0025, 'wo')
rpv_steel.add_nuclide("Cu63", 0.0013696, 'wo')
rpv_steel.add_nuclide("Cu65", 0.0006304, 'wo')
lower_rad_ref = openmc.Material(name='Lower radial reflector',
material_id=6)
lower_rad_ref.set_density('g/cm3', 4.32)
lower_rad_ref.add_nuclide("H1", 0.0095661, 'wo')
lower_rad_ref.add_nuclide("O16", 0.0759107, 'wo')
lower_rad_ref.add_nuclide("B10", 3.08409e-5, 'wo')
lower_rad_ref.add_nuclide("B11", 1.40499e-4, 'wo')
lower_rad_ref.add_nuclide("Fe54", 0.035620772088, 'wo')
lower_rad_ref.add_nuclide("Fe56", 0.579805982228, 'wo')
lower_rad_ref.add_nuclide("Fe57", 0.01362750048, 'wo')
lower_rad_ref.add_nuclide("Fe58", 0.001848545204, 'wo')
lower_rad_ref.add_nuclide("Ni58", 0.055298376566, 'wo')
lower_rad_ref.add_nuclide("Ni60", 0.022034425592, 'wo')
lower_rad_ref.add_nuclide("Ni61", 0.000973510811, 'wo')
lower_rad_ref.add_nuclide("Ni62", 0.003155886695, 'wo')
lower_rad_ref.add_nuclide("Ni64", 0.000829500336, 'wo')
lower_rad_ref.add_nuclide("Mn55", 0.0182870, 'wo')
lower_rad_ref.add_nuclide("Si28", 0.00839976771, 'wo')
lower_rad_ref.add_nuclide("Si29", 0.00044199679, 'wo')
lower_rad_ref.add_nuclide("Si30", 0.0003017355, 'wo')
lower_rad_ref.add_nuclide("Cr50", 0.007251360806, 'wo')
lower_rad_ref.add_nuclide("Cr52", 0.145407678031, 'wo')
lower_rad_ref.add_nuclide("Cr53", 0.016806340306, 'wo')
lower_rad_ref.add_nuclide("Cr54", 0.004261520857, 'wo')
lower_rad_ref.add_s_alpha_beta('c_H_in_H2O')
upper_rad_ref = openmc.Material(name='Upper radial reflector /'
'Top plate region', material_id=7)
upper_rad_ref.set_density('g/cm3', 4.28)
upper_rad_ref.add_nuclide("H1", 0.0086117, 'wo')
upper_rad_ref.add_nuclide("O16", 0.0683369, 'wo')
upper_rad_ref.add_nuclide("B10", 2.77638e-5, 'wo')
upper_rad_ref.add_nuclide("B11", 1.26481e-4, 'wo')
upper_rad_ref.add_nuclide("Fe54", 0.035953677186, 'wo')
upper_rad_ref.add_nuclide("Fe56", 0.585224740891, 'wo')
upper_rad_ref.add_nuclide("Fe57", 0.01375486056, 'wo')
upper_rad_ref.add_nuclide("Fe58", 0.001865821363, 'wo')
upper_rad_ref.add_nuclide("Ni58", 0.055815129186, 'wo')
upper_rad_ref.add_nuclide("Ni60", 0.022240333032, 'wo')
upper_rad_ref.add_nuclide("Ni61", 0.000982608081, 'wo')
upper_rad_ref.add_nuclide("Ni62", 0.003185377845, 'wo')
upper_rad_ref.add_nuclide("Ni64", 0.000837251856, 'wo')
upper_rad_ref.add_nuclide("Mn55", 0.0184579, 'wo')
upper_rad_ref.add_nuclide("Si28", 0.00847831314, 'wo')
upper_rad_ref.add_nuclide("Si29", 0.00044612986, 'wo')
upper_rad_ref.add_nuclide("Si30", 0.000304557, 'wo')
upper_rad_ref.add_nuclide("Cr50", 0.00731912987, 'wo')
upper_rad_ref.add_nuclide("Cr52", 0.146766614995, 'wo')
upper_rad_ref.add_nuclide("Cr53", 0.01696340737, 'wo')
upper_rad_ref.add_nuclide("Cr54", 0.004301347765, 'wo')
upper_rad_ref.add_s_alpha_beta('c_H_in_H2O')
bot_plate = openmc.Material(name='Bottom plate region', material_id=8)
bot_plate.set_density('g/cm3', 7.184)
bot_plate.add_nuclide("H1", 0.0011505, 'wo')
bot_plate.add_nuclide("O16", 0.0091296, 'wo')
bot_plate.add_nuclide("B10", 3.70915e-6, 'wo')
bot_plate.add_nuclide("B11", 1.68974e-5, 'wo')
bot_plate.add_nuclide("Fe54", 0.03855611055, 'wo')
bot_plate.add_nuclide("Fe56", 0.627585036425, 'wo')
bot_plate.add_nuclide("Fe57", 0.014750478, 'wo')
bot_plate.add_nuclide("Fe58", 0.002000875025, 'wo')
bot_plate.add_nuclide("Ni58", 0.059855207342, 'wo')
bot_plate.add_nuclide("Ni60", 0.023850159704, 'wo')
bot_plate.add_nuclide("Ni61", 0.001053732407, 'wo')
bot_plate.add_nuclide("Ni62", 0.003415945715, 'wo')
bot_plate.add_nuclide("Ni64", 0.000897854832, 'wo')
bot_plate.add_nuclide("Mn55", 0.0197940, 'wo')
bot_plate.add_nuclide("Si28", 0.00909197802, 'wo')
bot_plate.add_nuclide("Si29", 0.00047842098, 'wo')
bot_plate.add_nuclide("Si30", 0.000326601, 'wo')
bot_plate.add_nuclide("Cr50", 0.007848910646, 'wo')
bot_plate.add_nuclide("Cr52", 0.157390026871, 'wo')
bot_plate.add_nuclide("Cr53", 0.018191270146, 'wo')
bot_plate.add_nuclide("Cr54", 0.004612692337, 'wo')
bot_plate.add_s_alpha_beta('c_H_in_H2O')
bot_nozzle = openmc.Material(name='Bottom nozzle region', material_id=9)
bot_nozzle.set_density('g/cm3', 2.53)
bot_nozzle.add_nuclide("H1", 0.0245014, 'wo')
bot_nozzle.add_nuclide("O16", 0.1944274, 'wo')
bot_nozzle.add_nuclide("B10", 7.89917e-5, 'wo')
bot_nozzle.add_nuclide("B11", 3.59854e-4, 'wo')
bot_nozzle.add_nuclide("Fe54", 0.030411411144, 'wo')
bot_nozzle.add_nuclide("Fe56", 0.495012237964, 'wo')
bot_nozzle.add_nuclide("Fe57", 0.01163454624, 'wo')
bot_nozzle.add_nuclide("Fe58", 0.001578204652, 'wo')
bot_nozzle.add_nuclide("Ni58", 0.047211231662, 'wo')
bot_nozzle.add_nuclide("Ni60", 0.018811987544, 'wo')
bot_nozzle.add_nuclide("Ni61", 0.000831139127, 'wo')
bot_nozzle.add_nuclide("Ni62", 0.002694352115, 'wo')
bot_nozzle.add_nuclide("Ni64", 0.000708189552, 'wo')
bot_nozzle.add_nuclide("Mn55", 0.0156126, 'wo')
bot_nozzle.add_nuclide("Si28", 0.007171335558, 'wo')
bot_nozzle.add_nuclide("Si29", 0.000377356542, 'wo')
bot_nozzle.add_nuclide("Si30", 0.0002576079, 'wo')
bot_nozzle.add_nuclide("Cr50", 0.006190885148, 'wo')
bot_nozzle.add_nuclide("Cr52", 0.124142524198, 'wo')
bot_nozzle.add_nuclide("Cr53", 0.014348496148, 'wo')
bot_nozzle.add_nuclide("Cr54", 0.003638294506, 'wo')
bot_nozzle.add_s_alpha_beta('c_H_in_H2O')
top_nozzle = openmc.Material(name='Top nozzle region', material_id=10)
top_nozzle.set_density('g/cm3', 1.746)
top_nozzle.add_nuclide("H1", 0.0358870, 'wo')
top_nozzle.add_nuclide("O16", 0.2847761, 'wo')
top_nozzle.add_nuclide("B10", 1.15699e-4, 'wo')
top_nozzle.add_nuclide("B11", 5.27075e-4, 'wo')
top_nozzle.add_nuclide("Fe54", 0.02644016154, 'wo')
top_nozzle.add_nuclide("Fe56", 0.43037146399, 'wo')
top_nozzle.add_nuclide("Fe57", 0.0101152584, 'wo')
top_nozzle.add_nuclide("Fe58", 0.00137211607, 'wo')
top_nozzle.add_nuclide("Ni58", 0.04104621835, 'wo')
top_nozzle.add_nuclide("Ni60", 0.0163554502, 'wo')
top_nozzle.add_nuclide("Ni61", 0.000722605975, 'wo')
top_nozzle.add_nuclide("Ni62", 0.002342513875, 'wo')
top_nozzle.add_nuclide("Ni64", 0.0006157116, 'wo')
top_nozzle.add_nuclide("Mn55", 0.0135739, 'wo')
top_nozzle.add_nuclide("Si28", 0.006234853554, 'wo')
top_nozzle.add_nuclide("Si29", 0.000328078746, 'wo')
top_nozzle.add_nuclide("Si30", 0.0002239677, 'wo')
top_nozzle.add_nuclide("Cr50", 0.005382452306, 'wo')
top_nozzle.add_nuclide("Cr52", 0.107931450781, 'wo')
top_nozzle.add_nuclide("Cr53", 0.012474806806, 'wo')
top_nozzle.add_nuclide("Cr54", 0.003163190107, 'wo')
top_nozzle.add_s_alpha_beta('c_H_in_H2O')
top_fa = openmc.Material(name='Top of fuel assemblies', material_id=11)
top_fa.set_density('g/cm3', 3.044)
top_fa.add_nuclide("H1", 0.0162913, 'wo')
top_fa.add_nuclide("O16", 0.1292776, 'wo')
top_fa.add_nuclide("B10", 5.25228e-5, 'wo')
top_fa.add_nuclide("B11", 2.39272e-4, 'wo')
top_fa.add_nuclide("Zr90", 0.43313403903, 'wo')
top_fa.add_nuclide("Zr91", 0.09549277374, 'wo')
top_fa.add_nuclide("Zr92", 0.14759527104, 'wo')
top_fa.add_nuclide("Zr94", 0.15280552077, 'wo')
top_fa.add_nuclide("Zr96", 0.02511169542, 'wo')
top_fa.add_s_alpha_beta('c_H_in_H2O')
bot_fa = openmc.Material(name='Bottom of fuel assemblies', material_id=12)
bot_fa.set_density('g/cm3', 1.762)
bot_fa.add_nuclide("H1", 0.0292856, 'wo')
bot_fa.add_nuclide("O16", 0.2323919, 'wo')
bot_fa.add_nuclide("B10", 9.44159e-5, 'wo')
bot_fa.add_nuclide("B11", 4.30120e-4, 'wo')
bot_fa.add_nuclide("Zr90", 0.3741373658, 'wo')
bot_fa.add_nuclide("Zr91", 0.0824858164, 'wo')
bot_fa.add_nuclide("Zr92", 0.1274914944, 'wo')
bot_fa.add_nuclide("Zr94", 0.1319920622, 'wo')
bot_fa.add_nuclide("Zr96", 0.0216912612, 'wo')
bot_fa.add_s_alpha_beta('c_H_in_H2O')
# Define the materials file.
materials = openmc.Materials()
materials.default_xs = '71c'
materials += [fuel, clad, cold_water, hot_water, rpv_steel,
lower_rad_ref, upper_rad_ref, bot_plate,
bot_nozzle, top_nozzle, top_fa, bot_fa]
materials.export_to_xml()
# Define surfaces.
s1 = openmc.ZCylinder(R=0.41, surface_id=1)
s2 = openmc.ZCylinder(R=0.475, surface_id=2)
s3 = openmc.ZCylinder(R=0.56, surface_id=3)
s4 = openmc.ZCylinder(R=0.62, surface_id=4)
s5 = openmc.ZCylinder(R=187.6, surface_id=5)
s6 = openmc.ZCylinder(R=209.0, surface_id=6)
s7 = openmc.ZCylinder(R=229.0, surface_id=7)
s8 = openmc.ZCylinder(R=249.0, surface_id=8)
s8.boundary_type = 'vacuum'
s31 = openmc.ZPlane(z0=-229.0, surface_id=31)
s31.boundary_type = 'vacuum'
s32 = openmc.ZPlane(z0=-199.0, surface_id=32)
s33 = openmc.ZPlane(z0=-193.0, surface_id=33)
s34 = openmc.ZPlane(z0=-183.0, surface_id=34)
s35 = openmc.ZPlane(z0=0.0, surface_id=35)
s36 = openmc.ZPlane(z0=183.0, surface_id=36)
s37 = openmc.ZPlane(z0=203.0, surface_id=37)
s38 = openmc.ZPlane(z0=215.0, surface_id=38)
s39 = openmc.ZPlane(z0=223.0, surface_id=39)
s39.boundary_type = 'vacuum'
# Define pin cells.
c21 = openmc.Cell(cell_id=21, fill=fuel, region=-s1)
c22 = openmc.Cell(cell_id=22, fill=clad, region=+s1 & -s2)
c23 = openmc.Cell(cell_id=23, fill=cold_water, region=+s2)
fuel_cold = openmc.Universe(name='Fuel pin, cladding, cold water',
universe_id=1, cells=(c21, c22, c23))
c24 = openmc.Cell(cell_id=24, fill=cold_water, region=-s3)
c25 = openmc.Cell(cell_id=25, fill=clad, region=+s3 & -s4)
c26 = openmc.Cell(cell_id=26, fill=cold_water, region=+s4)
tube_cold = openmc.Universe(name='Instrumentation guide tube, cold water',
universe_id=2, cells=(c24, c25, c26))
c27 = openmc.Cell(cell_id=27, fill=fuel, region=-s1)
c28 = openmc.Cell(cell_id=28, fill=clad, region=+s1 & -s2)
c29 = openmc.Cell(cell_id=29, fill=hot_water, region=+s2)
fuel_hot = openmc.Universe(name='Fuel pin, cladding, hot water',
universe_id=3, cells=(c27, c28, c29))
c30 = openmc.Cell(cell_id=30, fill=hot_water, region=-s3)
c31 = openmc.Cell(cell_id=31, fill=clad, region=+s3 & -s4)
c32 = openmc.Cell(cell_id=32, fill=hot_water, region=+s4)
tube_hot = openmc.Universe(name='Instrumentation guide tube, hot water',
universe_id=4, cells=(c30, c31, c32))
guide_tubes = [(2, 5), (2, 8), (2, 11), (3, 3), (3, 13),
(5, 2), (5, 5), (5, 8), (5, 11), (5, 14),
(8, 2), (8, 5), (8, 8), (8, 11), (8, 14),
(11, 2), (11, 5), (11, 8), (11, 11), (11, 14),
(13, 3), (13, 13), (14, 5), (14, 8), (14, 11)]
# Define fuel lattices.
l100 = openmc.RectLattice(name='Fuel assembly (lower half)', lattice_id=100)
l100.lower_left = (-10.71, -10.71)
l100.pitch = (1.26, 1.26)
l100.universes = np.tile(fuel_cold, (17, 17))
for position in guide_tubes:
l100.universes[position] = tube_cold
l101 = openmc.RectLattice(name='Fuel assembly (upper half)', lattice_id=101)
l101.lower_left = (-10.71, -10.71)
l101.pitch = (1.26, 1.26)
l101.universes = np.tile(fuel_hot, (17, 17))
for position in guide_tubes:
l101.universes[position] = tube_hot
# Define assemblies.
c50 = openmc.Cell(cell_id=50, fill=cold_water, region=+s34 & -s35)
fa_cw = openmc.Universe(name='Water assembly (cold)', universe_id=5, cells=[c50])
c70 = openmc.Cell(cell_id=70, fill=hot_water, region=+s35 & -s36)
fa_hw = openmc.Universe(name='Water assembly (hot)', universe_id=7, cells=[c70])
c60 = openmc.Cell(cell_id=60, fill=l100, region=+s34 & -s35)
fa_cold = openmc.Universe(name='Fuel assembly (cold)', universe_id=6, cells=[c60])
c80 = openmc.Cell(cell_id=80, fill=l101, region=+s35 & -s36)
fa_hot = openmc.Universe(name='Fuel assembly (hot)', universe_id=8, cells=[c80])
# Define core lattices
l200 = openmc.RectLattice(name='Core lattice (lower half)', lattice_id=200)
l200.lower_left = (-224.91, -224.91)
l200.pitch = (21.42, 21.42)
l200.universes = [
[fa_cw]*21,
[fa_cw]*21,
[fa_cw]*7 + [fa_cold]*7 + [fa_cw]*7,
[fa_cw]*5 + [fa_cold]*11 + [fa_cw]*5,
[fa_cw]*4 + [fa_cold]*13 + [fa_cw]*4,
[fa_cw]*3 + [fa_cold]*15 + [fa_cw]*3,
[fa_cw]*3 + [fa_cold]*15 + [fa_cw]*3,
[fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2,
[fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2,
[fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2,
[fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2,
[fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2,
[fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2,
[fa_cw]*2 + [fa_cold]*17 + [fa_cw]*2,
[fa_cw]*3 + [fa_cold]*15 + [fa_cw]*3,
[fa_cw]*3 + [fa_cold]*15 + [fa_cw]*3,
[fa_cw]*4 + [fa_cold]*13 + [fa_cw]*4,
[fa_cw]*5 + [fa_cold]*11 + [fa_cw]*5,
[fa_cw]*7 + [fa_cold]*7 + [fa_cw]*7,
[fa_cw]*21,
[fa_cw]*21]
l201 = openmc.RectLattice(name='Core lattice (lower half)', lattice_id=201)
l201.lower_left = (-224.91, -224.91)
l201.pitch = (21.42, 21.42)
l201.universes = [
[fa_hw]*21,
[fa_hw]*21,
[fa_hw]*7 + [fa_hot]*7 + [fa_hw]*7,
[fa_hw]*5 + [fa_hot]*11 + [fa_hw]*5,
[fa_hw]*4 + [fa_hot]*13 + [fa_hw]*4,
[fa_hw]*3 + [fa_hot]*15 + [fa_hw]*3,
[fa_hw]*3 + [fa_hot]*15 + [fa_hw]*3,
[fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2,
[fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2,
[fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2,
[fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2,
[fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2,
[fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2,
[fa_hw]*2 + [fa_hot]*17 + [fa_hw]*2,
[fa_hw]*3 + [fa_hot]*15 + [fa_hw]*3,
[fa_hw]*3 + [fa_hot]*15 + [fa_hw]*3,
[fa_hw]*4 + [fa_hot]*13 + [fa_hw]*4,
[fa_hw]*5 + [fa_hot]*11 + [fa_hw]*5,
[fa_hw]*7 + [fa_hot]*7 + [fa_hw]*7,
[fa_hw]*21,
[fa_hw]*21]
# Define root universe
c1 = openmc.Cell(cell_id=1, fill=l200, region=-s6 & +s34 & -s35)
c2 = openmc.Cell(cell_id=2, fill=l201, region=-s6 & +s35 & -s36)
c3 = openmc.Cell(cell_id=3, fill=bot_plate, region=-s7 & +s31 & -s32)
c4 = openmc.Cell(cell_id=4, fill=bot_nozzle, region=-s5 & +s32 & -s33)
c5 = openmc.Cell(cell_id=5, fill=bot_fa, region=-s5 & +s33 & -s34)
c6 = openmc.Cell(cell_id=6, fill=top_fa, region=-s5 & +s36 & -s37)
c7 = openmc.Cell(cell_id=7, fill=top_nozzle, region=-s5 & +s37 & -s38)
c8 = openmc.Cell(cell_id=8, fill=upper_rad_ref, region=-s7 & +s38 & -s39)
c9 = openmc.Cell(cell_id=9, fill=bot_nozzle, region=+s6 & -s7 & +s32 & -s38)
c10 = openmc.Cell(cell_id=10, fill=rpv_steel, region=+s7 & -s8 & +s31 & -s39)
c11 = openmc.Cell(cell_id=11, fill=lower_rad_ref, region=+s5 & -s6 & +s32 & -s34)
c12 = openmc.Cell(cell_id=12, fill=upper_rad_ref, region=+s5 & -s6 & +s36 & -s38)
root = openmc.Universe(universe_id=0, name='root universe',
cells=(c1, c2, c3, c4, c5, c6, c7, c8, c9, c10, c11, c12))
# Create and export geometry
geometry = openmc.Geometry(root)
geometry.export_to_xml()
settings = openmc.Settings()
settings.batches = 10
settings.inactive = 5
settings.particles = 1000
settings.source = openmc.Source(space=openmc.stats.Box(
[-160, -160, -183], [160, 160, 183]))
settings.export_to_xml()
plot = openmc.Plot()
plot.filename = 'mat'
plot.origin = (125, 125, 0)
plot.width = (250, 250)
plot.pixels = (3000, 3000)
plot.color = 'mat'
plots = openmc.Plots([plot])
plots.export_to_xml()

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@ -0,0 +1,39 @@
#!/usr/bin/env python
import openmc
# Set up list of assembly positions
assemblies = ([(1,i) for i in range(6,13)] +
[(2,i) for i in range(4,15)] +
[(3,i) for i in range(3,16)] +
[(4,i) for i in range(2,17)] +
[(5,i) for i in range(2,17)] +
[(6,i) for i in range(1,18)] +
[(7,i) for i in range(1,18)] +
[(8,i) for i in range(1,18)] +
[(9,i) for i in range(1,18)] +
[(10,i) for i in range(1,18)] +
[(11,i) for i in range(1,18)] +
[(12,i) for i in range(1,18)] +
[(13,i) for i in range(2,17)] +
[(14,i) for i in range(2,17)] +
[(15,i) for i in range(3,16)] +
[(16,i) for i in range(4,15)] +
[(17,i) for i in range(6,13)])
# Write meshes and assemblies
tallies = openmc.Tallies()
for i, assem in enumerate(assemblies):
x, y = assem
mesh = openmc.Mesh()
mesh.lower_left = (-182.07 + 21.42*(x-1), -182.07 + 21.42*(y-1))
mesh.width = (1.26, 1.26)
mesh.dimension = (17, 17)
tally = openmc.Tally()
tally.filters = [openmc.MeshFilter(mesh)]
tally.nuclides = ['all']
tally.scores = ['total']
tallies.append(tally)
tallies.export_to_xml()

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