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Updated existing files to work with OpenMC 0.13.3

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This commit is contained in:
Adam Parler 2023-10-19 03:08:53 -07:00
parent 90f6fd7132
commit 70696eec41
27 changed files with 1029 additions and 778 deletions
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98
AP1000/PWR 2.1/problem/materials.xml
View file

@ -3,80 +3,82 @@
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 -->
<material id="1">
<density value="10.5" units="g/cc" />
<nuclide name="U-235" xs="71c" wo="0.0185105302348" />
<nuclide name="U-238" xs="71c" wo="0.862943290471" />
<nuclide name="O-16" xs="71c" wo="0.118546179294" />
<nuclide name="U235" xs="71c" wo="0.0185105302348" />
<nuclide name="U238" xs="71c" wo="0.862943290471" />
<nuclide name="O16" xs="71c" wo="0.118546179294" />
</material>
<!-- Helium for gap -->
<material id="2">
<density value="1.00000e-4" units="atom/b-cm" />
<nuclide name="He-4" xs="71c" ao="1.0" />
<nuclide name="He4" 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" />
<nuclide name="O16" xs="71c" wo="0.00125" />
<nuclide name="Nb93" xs="71c" wo="0.01" />
<nuclide name="Sn112" xs="71c" wo="0.000097" />
<nuclide name="Sn114" xs="71c" wo="0.000066" />
<nuclide name="Sn115" xs="71c" wo="0.000034" />
<nuclide name="Sn116" xs="71c" wo="0.001454" />
<nuclide name="Sn117" xs="71c" wo="0.000768" />
<nuclide name="Sn118" xs="71c" wo="0.002422 " />
<nuclide name="Sn119" xs="71c" wo="0.000859" />
<nuclide name="Sn120" xs="71c" wo="0.003258" />
<nuclide name="Sn122" xs="71c" wo="0.000463" />
<nuclide name="Sn124" xs="71c" wo="0.000579" />
<nuclide name="Fe54" xs="71c" wo="0.00005845" />
<nuclide name="Fe56" xs="71c" wo="0.00091754" />
<nuclide name="Fe57" xs="71c" wo="0.00002119" />
<nuclide name="Fe58" xs="71c" wo="0.00000282" />
<nuclide name="Zr90" xs="71c" wo="0.503052375" />
<nuclide name="Zr91" xs="71c" wo="0.10970355" />
<nuclide name="Zr92" xs="71c" wo="0.167684125" />
<nuclide name="Zr94" xs="71c" wo="0.16993295" />
<nuclide name="Zr96" 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" />
<nuclide name="H1" xs="71c" ao="2.0" />
<nuclide name="O16" xs="71c" ao="1.0" />
<sab name="c_H_in_H2O" xs="04t" />
</material>
<!-- Guide Tube -->
<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" />
<nuclide name="Fe-56" xs="71c" wo="0.63762775" />
<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" />
<nuclide name="Ni58" xs="71c" wo="0.06467315" />
<nuclide name="Ni60" xs="71c" wo="0.02492135" />
<nuclide name="Ni61" xs="71c" wo="0.001082905" />
<nuclide name="Ni62" xs="71c" wo="0.00345287" />
<nuclide name="Ni64" xs="71c" wo="0.000879225" />
<nuclide name="Fe54" xs="71c" wo="0.04062275" />
<nuclide name="Fe56" xs="71c" wo="0.63762775" />
<nuclide name="Fe57" xs="71c" wo="0.01472705" />
<nuclide name="Fe58" xs="71c" wo="0.0019599" />
<nuclide name="Mn55" xs="71c" wo="0.020" />
<nuclide name="Cr50" xs="71c" wo="0.0082555" />
<nuclide name="Cr52" xs="71c" wo="0.1591991" />
<nuclide name="Cr53" xs="71c" wo="0.0180519" />
<nuclide name="Cr54" xs="71c" wo="0.0044935" />
</material>
</materials>

4
AP1000/PWR 2.1/problem/settings.xml
View file

@ -3,14 +3,12 @@
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
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/NuclearCodes/Cross_section_data/nndc/293.6K/cross_sections_mcnp6.1.xml</cross_sections>
<eigenvalue>
<batches>600</batches>

68
AP1000/PWR 2.1/problem/tallies.xml
View file

@ -1,47 +1,77 @@
<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>1</bins>
</filter>
<filter id="3" type="cell">
<bins>1</bins>
</filter>
<filter id="4" type="cell">
<bins>1</bins>
</filter>
<filter id="5" type="cell">
<bins>1</bins>
</filter>
<filter id="6" type="cell">
<bins>1</bins>
</filter>
<filter id="7" type="cell">
<bins>1</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filter type="cell" bins="1" />
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="1" />
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="1" />
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="1" />
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="1" />
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="1" />
<tally id="7">
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

98
AP1000/PWR 2.6/problem/materials.xml
View file

@ -3,80 +3,82 @@
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 -->
<material id="1">
<density value="10.5" units="g/cc" />
<nuclide name="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" />
<nuclide name="U235" xs="71c" wo="0.0229176" />
<nuclide name="U238" xs="71c" wo="0.858529" />
<nuclide name="O16" 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" />
<nuclide name="He4" 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" />
<nuclide name="O16" xs="71c" wo="0.00125" />
<nuclide name="Nb93" xs="71c" wo="0.01" />
<nuclide name="Sn112" xs="71c" wo="0.000097" />
<nuclide name="Sn114" xs="71c" wo="0.000066" />
<nuclide name="Sn115" xs="71c" wo="0.000034" />
<nuclide name="Sn116" xs="71c" wo="0.001454" />
<nuclide name="Sn117" xs="71c" wo="0.000768" />
<nuclide name="Sn118" xs="71c" wo="0.002422 " />
<nuclide name="Sn119" xs="71c" wo="0.000859" />
<nuclide name="Sn120" xs="71c" wo="0.003258" />
<nuclide name="Sn122" xs="71c" wo="0.000463" />
<nuclide name="Sn124" xs="71c" wo="0.000579" />
<nuclide name="Fe54" xs="71c" wo="0.00005845" />
<nuclide name="Fe56" xs="71c" wo="0.00091754" />
<nuclide name="Fe57" xs="71c" wo="0.00002119" />
<nuclide name="Fe58" xs="71c" wo="0.00000282" />
<nuclide name="Zr90" xs="71c" wo="0.503052375" />
<nuclide name="Zr91" xs="71c" wo="0.10970355" />
<nuclide name="Zr92" xs="71c" wo="0.167684125" />
<nuclide name="Zr94" xs="71c" wo="0.16993295" />
<nuclide name="Zr96" 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" />
<nuclide name="H1" xs="71c" ao="2.0" />
<nuclide name="O16" xs="71c" ao="1.0" />
<sab name="c_H_in_H2O" xs="04t" />
</material>
<!-- Guide Tube -->
<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" />
<nuclide name="Fe-56" xs="71c" wo="0.63762775" />
<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" />
<nuclide name="Ni58" xs="71c" wo="0.06467315" />
<nuclide name="Ni60" xs="71c" wo="0.02492135" />
<nuclide name="Ni61" xs="71c" wo="0.001082905" />
<nuclide name="Ni62" xs="71c" wo="0.00345287" />
<nuclide name="Ni64" xs="71c" wo="0.000879225" />
<nuclide name="Fe54" xs="71c" wo="0.04062275" />
<nuclide name="Fe56" xs="71c" wo="0.63762775" />
<nuclide name="Fe57" xs="71c" wo="0.01472705" />
<nuclide name="Fe58" xs="71c" wo="0.0019599" />
<nuclide name="Mn55" xs="71c" wo="0.020" />
<nuclide name="Cr50" xs="71c" wo="0.0082555" />
<nuclide name="Cr52" xs="71c" wo="0.1591991" />
<nuclide name="Cr53" xs="71c" wo="0.0180519" />
<nuclide name="Cr54" xs="71c" wo="0.0044935" />
</material>
</materials>

7
AP1000/PWR 2.6/problem/settings.xml
View file

@ -3,18 +3,13 @@
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
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>

66
AP1000/PWR 2.6/problem/tallies.xml
View file

@ -1,47 +1,77 @@
<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>1</bins>
</filter>
<filter id="3" type="cell">
<bins>1</bins>
</filter>
<filter id="4" type="cell">
<bins>1</bins>
</filter>
<filter id="5" type="cell">
<bins>1</bins>
</filter>
<filter id="6" type="cell">
<bins>1</bins>
</filter>
<filter id="7" type="cell">
<bins>1</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filter type="cell" bins="1" />
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="1" />
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="1" />
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="1" />
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="1" />
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="1" />
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

98
AP1000/PWR 3.10/problem/materials.xml
View file

@ -3,80 +3,82 @@
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
Description: AP1000 PWR Assembly 17*17
Case: Problem 2 (17*17 PWR Assembly)
Written By: Ahmed K Madani
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 -->
<material id="1">
<density value="10.5" units="g/cc" />
<nuclide name="U-235" xs="71c" wo="0.0273246599755" />
<nuclide name="U-238" xs="71c" wo="0.854115984395" />
<nuclide name="O-16" xs="71c" wo="0.11855935563" />
<nuclide name="U235" xs="71c" wo="0.0273246599755" />
<nuclide name="U238" xs="71c" wo="0.854115984395" />
<nuclide name="O16" xs="71c" wo="0.11855935563" />
</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" />
<nuclide name="He4" 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" />
<nuclide name="O16" xs="71c" wo="0.00125" />
<nuclide name="Nb93" xs="71c" wo="0.01" />
<nuclide name="Sn112" xs="71c" wo="0.000097" />
<nuclide name="Sn114" xs="71c" wo="0.000066" />
<nuclide name="Sn115" xs="71c" wo="0.000034" />
<nuclide name="Sn116" xs="71c" wo="0.001454" />
<nuclide name="Sn117" xs="71c" wo="0.000768" />
<nuclide name="Sn118" xs="71c" wo="0.002422 " />
<nuclide name="Sn119" xs="71c" wo="0.000859" />
<nuclide name="Sn120" xs="71c" wo="0.003258" />
<nuclide name="Sn122" xs="71c" wo="0.000463" />
<nuclide name="Sn124" xs="71c" wo="0.000579" />
<nuclide name="Fe54" xs="71c" wo="0.00005845" />
<nuclide name="Fe56" xs="71c" wo="0.00091754" />
<nuclide name="Fe57" xs="71c" wo="0.00002119" />
<nuclide name="Fe58" xs="71c" wo="0.00000282" />
<nuclide name="Zr90" xs="71c" wo="0.503052375" />
<nuclide name="Zr91" xs="71c" wo="0.10970355" />
<nuclide name="Zr92" xs="71c" wo="0.167684125" />
<nuclide name="Zr94" xs="71c" wo="0.16993295" />
<nuclide name="Zr96" 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" />
<nuclide name="H1" xs="71c" ao="2.0" />
<nuclide name="O16" xs="71c" ao="1.0" />
<sab name="c_H_in_H2O" xs="04t" />
</material>
<!-- Guide Tube -->
<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" />
<nuclide name="Fe-56" xs="71c" wo="0.63762775" />
<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" />
<nuclide name="Ni58" xs="71c" wo="0.06467315" />
<nuclide name="Ni60" xs="71c" wo="0.02492135" />
<nuclide name="Ni61" xs="71c" wo="0.001082905" />
<nuclide name="Ni62" xs="71c" wo="0.00345287" />
<nuclide name="Ni64" xs="71c" wo="0.000879225" />
<nuclide name="Fe54" xs="71c" wo="0.04062275" />
<nuclide name="Fe56" xs="71c" wo="0.63762775" />
<nuclide name="Fe57" xs="71c" wo="0.01472705" />
<nuclide name="Fe58" xs="71c" wo="0.0019599" />
<nuclide name="Mn55" xs="71c" wo="0.020" />
<nuclide name="Cr50" xs="71c" wo="0.0082555" />
<nuclide name="Cr52" xs="71c" wo="0.1591991" />
<nuclide name="Cr53" xs="71c" wo="0.0180519" />
<nuclide name="Cr54" xs="71c" wo="0.0044935" />
</material>
</materials>

7
AP1000/PWR 3.10/problem/settings.xml
View file

@ -3,18 +3,13 @@
<!--
====================================================
Description: AP1000 PWR Assembly 17*17
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>

69
AP1000/PWR 3.10/problem/tallies.xml
View file

@ -1,46 +1,77 @@
<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>1</bins>
</filter>
<filter id="3" type="cell">
<bins>1</bins>
</filter>
<filter id="4" type="cell">
<bins>1</bins>
</filter>
<filter id="5" type="cell">
<bins>1</bins>
</filter>
<filter id="6" type="cell">
<bins>1</bins>
</filter>
<filter id="7" type="cell">
<bins>1</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filter type="cell" bins="1" />
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="1" />
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="1" />
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="1" />
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="1" />
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="1" />
<tally id="7">
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

188
ARC700/CANDU 2.1/problem/materials.xml
View file

@ -9,142 +9,144 @@
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<material id="11">
<density value="9.82" units="g/cc" />
<nuclide name="U-235" xs="73c" wo="2.1" />
<nuclide name="U-238" xs="73c" wo="97.9" />
<nuclide name="O-16" xs="73c" wo="13.4529" />
<nuclide name="U235" xs="73c" wo="2.1" />
<nuclide name="U238" xs="73c" wo="97.9" />
<nuclide name="O16" xs="73c" wo="13.4529" />
</material>
<material id="12">
<density value="9.82" units="g/cc" />
<nuclide name="U-235" xs="72c" wo="2.1" />
<nuclide name="U-238" xs="72c" wo="97.9" />
<nuclide name="O-16" xs="72c" wo="13.4529" />
<nuclide name="U235" xs="72c" wo="2.1" />
<nuclide name="U238" xs="72c" wo="97.9" />
<nuclide name="O16" xs="72c" wo="13.4529" />
</material>
<material id="13">
<density value="10.298" units="g/cc" />
<nuclide name="U-235" xs="72c" wo="2.1" />
<nuclide name="U-238" xs="72c" wo="97.9" />
<nuclide name="O-16" xs="72c" wo="13.4529" />
<nuclide name="U235" xs="72c" wo="2.1" />
<nuclide name="U238" xs="72c" wo="97.9" />
<nuclide name="O16" xs="72c" wo="13.4529" />
</material>
<material id="14">
<density value="10.298" units="g/cc" />
<nuclide name="U-235" xs="72c" wo="0.72" />
<nuclide name="U-238" xs="72c" wo="99.28" />
<nuclide name="O-16" xs="72c" wo="13.4529" />
<nuclide name="Dy-160" xs="72c" wo="0.1735" />
<nuclide name="Dy-161" xs="72c" wo="1.418" />
<nuclide name="Dy-162" xs="72c" wo="1.915" />
<nuclide name="Dy-163" xs="72c" wo="1.861" />
<nuclide name="Dy-164" xs="72c" wo="2.1317" />
<nuclide name="U235" xs="72c" wo="0.72" />
<nuclide name="U238" xs="72c" wo="99.28" />
<nuclide name="O16" xs="72c" wo="13.4529" />
<nuclide name="Dy160" xs="72c" wo="0.1735" />
<nuclide name="Dy161" xs="72c" wo="1.418" />
<nuclide name="Dy162" xs="72c" wo="1.915" />
<nuclide name="Dy163" xs="72c" wo="1.861" />
<nuclide name="Dy164" xs="72c" wo="2.1317" />
</material>
<!-- Zircaloy 4 -->
<material id="2">
<density value="7.48" units="g/cc" />
<nuclide name="O-16" xs="71c" wo="0.125" />
<nuclide name="Cr-50" xs="71c" wo="0.004345" />
<nuclide name="Cr-52" xs="71c" wo="0.083789" />
<nuclide name="Cr-53" xs="71c" wo="0.009501" />
<nuclide name="Cr-54" xs="71c" wo="0.002365" />
<nuclide name="Sn-112" xs="71c" wo="0.014065" />
<nuclide name="Sn-114" xs="71c" wo="0.00957" />
<nuclide name="Sn-115" xs="71c" wo="0.00493" />
<nuclide name="Sn-116" xs="71c" wo="0.21083" />
<nuclide name="Sn-117" xs="71c" wo="0.11136" />
<nuclide name="Sn-118" xs="71c" wo="0.35119" />
<nuclide name="Sn-119" xs="71c" wo="0.124555" />
<nuclide name="Sn-120" xs="71c" wo="0.47241" />
<nuclide name="Sn-122" xs="71c" wo="0.067135" />
<nuclide name="Sn-124" xs="71c" wo="0.083955" />
<nuclide name="Fe-54" xs="71c" wo="0.0122745" />
<nuclide name="Fe-56" xs="71c" wo="0.1926834" />
<nuclide name="Fe-57" xs="71c" wo="0.0044499" />
<nuclide name="Fe-58" xs="71c" wo="0.0005922" />
<nuclide name="Zr-90" xs="71c" wo="50.48" />
<nuclide name="Zr-91" xs="71c" wo="11" />
<nuclide name="Zr-92" xs="71c" wo="16.83" />
<nuclide name="Zr-94" xs="71c" wo="17.05" />
<nuclide name="Zr-96" xs="71c" wo="2.75" />
<nuclide name="O16" xs="71c" wo="0.125" />
<nuclide name="Cr50" xs="71c" wo="0.004345" />
<nuclide name="Cr52" xs="71c" wo="0.083789" />
<nuclide name="Cr53" xs="71c" wo="0.009501" />
<nuclide name="Cr54" xs="71c" wo="0.002365" />
<nuclide name="Sn112" xs="71c" wo="0.014065" />
<nuclide name="Sn114" xs="71c" wo="0.00957" />
<nuclide name="Sn115" xs="71c" wo="0.00493" />
<nuclide name="Sn116" xs="71c" wo="0.21083" />
<nuclide name="Sn117" xs="71c" wo="0.11136" />
<nuclide name="Sn118" xs="71c" wo="0.35119" />
<nuclide name="Sn119" xs="71c" wo="0.124555" />
<nuclide name="Sn120" xs="71c" wo="0.47241" />
<nuclide name="Sn122" xs="71c" wo="0.067135" />
<nuclide name="Sn124" xs="71c" wo="0.083955" />
<nuclide name="Fe54" xs="71c" wo="0.0122745" />
<nuclide name="Fe56" xs="71c" wo="0.1926834" />
<nuclide name="Fe57" xs="71c" wo="0.0044499" />
<nuclide name="Fe58" xs="71c" wo="0.0005922" />
<nuclide name="Zr90" xs="71c" wo="50.48" />
<nuclide name="Zr91" xs="71c" wo="11" />
<nuclide name="Zr92" xs="71c" wo="16.83" />
<nuclide name="Zr94" xs="71c" wo="17.05" />
<nuclide name="Zr96" xs="71c" wo="2.75" />
</material>
<!-- water -->
<material id="3">
<density value="0.71273" units="g/cc" />
<nuclide name="H-1" ao="0.6666" />
<nuclide name="O-16" ao="0.3334" />
<sab name="lwtr" xs="15t" />
<nuclide name="H1" ao="0.6666" />
<nuclide name="O16" ao="0.3334" />
<sab name="c_H_in_H2O" xs="15t" />
</material>
<!-- pressure tubr zr + Nb-->
<material id="4">
<density value="6.57" units="g/cc" />
<nuclide name="Zr-90" xs="71c" wo="50.16" />
<nuclide name="Zr-91" xs="71c" wo="10.94" />
<nuclide name="Zr-92" xs="71c" wo="16.72" />
<nuclide name="Zr-94" xs="71c" wo="16.945" />
<nuclide name="Zr-96" xs="71c" wo="2.73" />
<nuclide name="Nb-93" xs="71c" wo="2.5" />
<nuclide name="Zr90" xs="71c" wo="50.16" />
<nuclide name="Zr91" xs="71c" wo="10.94" />
<nuclide name="Zr92" xs="71c" wo="16.72" />
<nuclide name="Zr94" xs="71c" wo="16.945" />
<nuclide name="Zr96" xs="71c" wo="2.73" />
<nuclide name="Nb93" xs="71c" wo="2.5" />
</material>
<!-- grph -->
<material id="5">
<density value="0.0017" units="g/cc" />
<nuclide name="O-16" ao="0.6666" />
<nuclide name="C-Nat" ao="0.3334" />
<sab name="grph" xs="11t" />
<nuclide name="O16" ao="0.6666" />
<nuclide name="CNat" ao="0.3334" />
<sab name="c_Graphite" xs="11t" />
</material>
<!--Calandria Zirconium alloy grade R60804 -->
<material id="6">
<density value="6.44" units="g/cc" />
<nuclide name="O-16" xs="70c" wo="0.125" />
<nuclide name="Cr-50" xs="70c" wo="0.004345" />
<nuclide name="Cr-52" xs="70c" wo="0.083789" />
<nuclide name="Cr-53" xs="70c" wo="0.009501" />
<nuclide name="Cr-54" xs="70c" wo="0.002365" />
<nuclide name="Sn-112" xs="70c" wo="0.014065" />
<nuclide name="Sn-114" xs="70c" wo="0.00957" />
<nuclide name="Sn-115" xs="70c" wo="0.00493" />
<nuclide name="Sn-116" xs="70c" wo="0.21083" />
<nuclide name="Sn-117" xs="70c" wo="0.11136" />
<nuclide name="Sn-118" xs="70c" wo="0.35119" />
<nuclide name="Sn-119" xs="70c" wo="0.124555" />
<nuclide name="Sn-120" xs="70c" wo="0.47241" />
<nuclide name="Sn-122" xs="70c" wo="0.067135" />
<nuclide name="Sn-124" xs="70c" wo="0.083955" />
<nuclide name="Fe-54" xs="70c" wo="0.0122745" />
<nuclide name="Fe-56" xs="70c" wo="0.1926834" />
<nuclide name="Fe-57" xs="70c" wo="0.004431" />
<nuclide name="Fe-58" xs="70c" wo="0.0005922" />
<nuclide name="Zr-90" xs="70c" wo="50.16" />
<nuclide name="Zr-91" xs="70c" wo="10.94" />
<nuclide name="Zr-92" xs="70c" wo="16.72" />
<nuclide name="Zr-94" xs="70c" wo="17.94" />
<nuclide name="Zr-96" xs="70c" wo="2.73" />
<density value="6.44" units="g/cc" />
<nuclide name="O16" xs="70c" wo="0.125" />
<nuclide name="Cr50" xs="70c" wo="0.004345" />
<nuclide name="Cr52" xs="70c" wo="0.083789" />
<nuclide name="Cr53" xs="70c" wo="0.009501" />
<nuclide name="Cr54" xs="70c" wo="0.002365" />
<nuclide name="Sn112" xs="70c" wo="0.014065" />
<nuclide name="Sn114" xs="70c" wo="0.00957" />
<nuclide name="Sn115" xs="70c" wo="0.00493" />
<nuclide name="Sn116" xs="70c" wo="0.21083" />
<nuclide name="Sn117" xs="70c" wo="0.11136" />
<nuclide name="Sn118" xs="70c" wo="0.35119" />
<nuclide name="Sn119" xs="70c" wo="0.124555" />
<nuclide name="Sn120" xs="70c" wo="0.47241" />
<nuclide name="Sn122" xs="70c" wo="0.067135" />
<nuclide name="Sn124" xs="70c" wo="0.083955" />
<nuclide name="Fe54" xs="70c" wo="0.0122745" />
<nuclide name="Fe56" xs="70c" wo="0.1926834" />
<nuclide name="Fe57" xs="70c" wo="0.004431" />
<nuclide name="Fe58" xs="70c" wo="0.0005922" />
<nuclide name="Zr90" xs="70c" wo="50.16" />
<nuclide name="Zr91" xs="70c" wo="10.94" />
<nuclide name="Zr92" xs="70c" wo="16.72" />
<nuclide name="Zr94" xs="70c" wo="17.94" />
<nuclide name="Zr96" xs="70c" wo="2.73" />
</material>
<!-- Heavy water -->
<material id="7">
<density value="1.07801" units="g/cc" />
<nuclide name="O-16" xs="73c" ao="1" />
<nuclide name="H-2" xs="80c" ao="1.996" />
<nuclide name="H-1" xs="80c" ao="0.004" />
<sab name="lwtr" xs="11t" />
<sab name="hwtr" xs="11t" />
<nuclide name="O16" xs="73c" ao="1" />
<nuclide name="H2" xs="80c" ao="1.996" />
<nuclide name="H1" xs="80c" ao="0.004" />
<sab name="c_H_in_H2O" xs="11t" />
<sab name="c_D_in_D2O" xs="11t" />
</material>
</materials>

4
ARC700/CANDU 2.1/problem/settings.xml
View file

@ -10,10 +10,6 @@
====================================================
-->
<cross_sections>
/home/ahmedk/Desktop/xdata/cross_sections1.xml
</cross_sections>
<!-- Parameters for k-eigenvalue calculation -->
<eigenvalue>
<batches>600</batches>

66
ARC700/CANDU 2.1/problem/tallies.xml
View file

@ -1,47 +1,77 @@
<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>93 87</bins>
</filter>
<filter id="2" type="cell">
<bins>93 87</bins>
</filter>
<filter id="3" type="cell">
<bins>93 87</bins>
</filter>
<filter id="4" type="cell">
<bins>93 87</bins>
</filter>
<filter id="5" type="cell">
<bins>93 87</bins>
</filter>
<filter id="6" type="cell">
<bins>93 87</bins>
</filter>
<filter id="7" type="cell">
<bins>93 87</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filter type="cell" bins="93 87" />
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="93 87" />
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="93 87" />
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="93 87" />
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="93 87" />
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="93 87" />
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="93 87" />
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

186
ARC700/CANDU 2.6/problem/materials.xml
View file

@ -9,142 +9,144 @@
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<material id="11">
<density value="9.82" units="g/cc" />
<nuclide name="U-235" xs="73c" wo="2.6" />
<nuclide name="U-238" xs="73c" wo="97.4" />
<nuclide name="O-16" xs="73c" wo="13.4529" />
<nuclide name="U235" xs="73c" wo="2.6" />
<nuclide name="U238" xs="73c" wo="97.4" />
<nuclide name="O16" xs="73c" wo="13.4529" />
</material>
<material id="12">
<density value="9.82" units="g/cc" />
<nuclide name="U-235" xs="72c" wo="2.6" />
<nuclide name="U-238" xs="72c" wo="97.4" />
<nuclide name="O-16" xs="72c" wo="13.4529" />
<nuclide name="U235" xs="72c" wo="2.6" />
<nuclide name="U238" xs="72c" wo="97.4" />
<nuclide name="O16" xs="72c" wo="13.4529" />
</material>
<material id="13">
<density value="10.298" units="g/cc" />
<nuclide name="U-235" xs="72c" wo="2.6" />
<nuclide name="U-238" xs="72c" wo="97.4" />
<nuclide name="U235" xs="72c" wo="2.6" />
<nuclide name="U238" xs="72c" wo="97.4" />
<nuclide name="O-16" xs="72c" wo="13.4529" />
</material>
<material id="14">
<density value="10.298" units="g/cc" />
<nuclide name="U-235" xs="72c" wo="0.72" />
<nuclide name="U-238" xs="72c" wo="99.28" />
<nuclide name="O-16" xs="72c" wo="13.4529" />
<nuclide name="Dy-160" xs="72c" wo="0.1735" />
<nuclide name="Dy-161" xs="72c" wo="1.418" />
<nuclide name="Dy-162" xs="72c" wo="1.915" />
<nuclide name="Dy-163" xs="72c" wo="1.861" />
<nuclide name="Dy-164" xs="72c" wo="2.1317" />
<nuclide name="U235" xs="72c" wo="0.72" />
<nuclide name="U238" xs="72c" wo="99.28" />
<nuclide name="O16" xs="72c" wo="13.4529" />
<nuclide name="Dy160" xs="72c" wo="0.1735" />
<nuclide name="Dy161" xs="72c" wo="1.418" />
<nuclide name="Dy162" xs="72c" wo="1.915" />
<nuclide name="Dy163" xs="72c" wo="1.861" />
<nuclide name="Dy164" xs="72c" wo="2.1317" />
</material>
<!-- Zircaloy 4 -->
<material id="2">
<density value="7.48" units="g/cc" />
<nuclide name="O-16" xs="71c" wo="0.125" />
<nuclide name="Cr-50" xs="71c" wo="0.004345" />
<nuclide name="Cr-52" xs="71c" wo="0.083789" />
<nuclide name="Cr-53" xs="71c" wo="0.009501" />
<nuclide name="Cr-54" xs="71c" wo="0.002365" />
<nuclide name="Sn-112" xs="71c" wo="0.014065" />
<nuclide name="Sn-114" xs="71c" wo="0.00957" />
<nuclide name="Sn-115" xs="71c" wo="0.00493" />
<nuclide name="Sn-116" xs="71c" wo="0.21083" />
<nuclide name="Sn-117" xs="71c" wo="0.11136" />
<nuclide name="Sn-118" xs="71c" wo="0.35119" />
<nuclide name="Sn-119" xs="71c" wo="0.124555" />
<nuclide name="Sn-120" xs="71c" wo="0.47241" />
<nuclide name="Sn-122" xs="71c" wo="0.067135" />
<nuclide name="Sn-124" xs="71c" wo="0.083955" />
<nuclide name="Fe-54" xs="71c" wo="0.0122745" />
<nuclide name="Fe-56" xs="71c" wo="0.1926834" />
<nuclide name="Fe-57" xs="71c" wo="0.0044499" />
<nuclide name="Fe-58" xs="71c" wo="0.0005922" />
<nuclide name="Zr-90" xs="71c" wo="50.48" />
<nuclide name="Zr-91" xs="71c" wo="11" />
<nuclide name="Zr-92" xs="71c" wo="16.83" />
<nuclide name="Zr-94" xs="71c" wo="17.05" />
<nuclide name="Zr-96" xs="71c" wo="2.75" />
<nuclide name="O16" xs="71c" wo="0.125" />
<nuclide name="Cr50" xs="71c" wo="0.004345" />
<nuclide name="Cr52" xs="71c" wo="0.083789" />
<nuclide name="Cr53" xs="71c" wo="0.009501" />
<nuclide name="Cr54" xs="71c" wo="0.002365" />
<nuclide name="Sn112" xs="71c" wo="0.014065" />
<nuclide name="Sn114" xs="71c" wo="0.00957" />
<nuclide name="Sn115" xs="71c" wo="0.00493" />
<nuclide name="Sn116" xs="71c" wo="0.21083" />
<nuclide name="Sn117" xs="71c" wo="0.11136" />
<nuclide name="Sn118" xs="71c" wo="0.35119" />
<nuclide name="Sn119" xs="71c" wo="0.124555" />
<nuclide name="Sn120" xs="71c" wo="0.47241" />
<nuclide name="Sn122" xs="71c" wo="0.067135" />
<nuclide name="Sn124" xs="71c" wo="0.083955" />
<nuclide name="Fe54" xs="71c" wo="0.0122745" />
<nuclide name="Fe56" xs="71c" wo="0.1926834" />
<nuclide name="Fe57" xs="71c" wo="0.0044499" />
<nuclide name="Fe58" xs="71c" wo="0.0005922" />
<nuclide name="Zr90" xs="71c" wo="50.48" />
<nuclide name="Zr91" xs="71c" wo="11" />
<nuclide name="Zr92" xs="71c" wo="16.83" />
<nuclide name="Zr94" xs="71c" wo="17.05" />
<nuclide name="Zr96" xs="71c" wo="2.75" />
</material>
<!-- water -->
<material id="3">
<density value="0.71273" units="g/cc" />
<nuclide name="H-1" ao="0.6666" />
<nuclide name="O-16" ao="0.3334" />
<sab name="lwtr" xs="15t" />
<nuclide name="H1" ao="0.6666" />
<nuclide name="O16" ao="0.3334" />
<sab name="c_H_in_H2O" xs="15t" />
</material>
<!-- pressure tubr zr + Nb-->
<material id="4">
<density value="6.57" units="g/cc" />
<nuclide name="Zr-90" xs="71c" wo="50.16" />
<nuclide name="Zr-91" xs="71c" wo="10.94" />
<nuclide name="Zr-92" xs="71c" wo="16.72" />
<nuclide name="Zr-94" xs="71c" wo="16.945" />
<nuclide name="Zr-96" xs="71c" wo="2.73" />
<nuclide name="Nb-93" xs="71c" wo="2.5" />
<nuclide name="Zr90" xs="71c" wo="50.16" />
<nuclide name="Zr91" xs="71c" wo="10.94" />
<nuclide name="Zr92" xs="71c" wo="16.72" />
<nuclide name="Zr94" xs="71c" wo="16.945" />
<nuclide name="Zr96" xs="71c" wo="2.73" />
<nuclide name="Nb93" xs="71c" wo="2.5" />
</material>
<!-- grph -->
<material id="5">
<density value="0.0017" units="g/cc" />
<nuclide name="O-16" ao="0.6666" />
<nuclide name="C-Nat" ao="0.3334" />
<sab name="grph" xs="11t" />
<nuclide name="O16" ao="0.6666" />
<nuclide name="CNat" ao="0.3334" />
<sab name="c_Graphite" xs="11t" />
</material>
<!--Calandria Zirconium alloy grade R60804 -->
<material id="6">
<density value="6.44" units="g/cc" />
<nuclide name="O-16" xs="70c" wo="0.125" />
<nuclide name="Cr-50" xs="70c" wo="0.004345" />
<nuclide name="Cr-52" xs="70c" wo="0.083789" />
<nuclide name="Cr-53" xs="70c" wo="0.009501" />
<nuclide name="Cr-54" xs="70c" wo="0.002365" />
<nuclide name="Sn-112" xs="70c" wo="0.014065" />
<nuclide name="Sn-114" xs="70c" wo="0.00957" />
<nuclide name="Sn-115" xs="70c" wo="0.00493" />
<nuclide name="Sn-116" xs="70c" wo="0.21083" />
<nuclide name="Sn-117" xs="70c" wo="0.11136" />
<nuclide name="Sn-118" xs="70c" wo="0.35119" />
<nuclide name="Sn-119" xs="70c" wo="0.124555" />
<nuclide name="Sn-120" xs="70c" wo="0.47241" />
<nuclide name="Sn-122" xs="70c" wo="0.067135" />
<nuclide name="Sn-124" xs="70c" wo="0.083955" />
<nuclide name="Fe-54" xs="70c" wo="0.0122745" />
<nuclide name="Fe-56" xs="70c" wo="0.1926834" />
<nuclide name="Fe-57" xs="70c" wo="0.004431" />
<nuclide name="Fe-58" xs="70c" wo="0.0005922" />
<nuclide name="Zr-90" xs="70c" wo="50.16" />
<nuclide name="Zr-91" xs="70c" wo="10.94" />
<nuclide name="Zr-92" xs="70c" wo="16.72" />
<nuclide name="Zr-94" xs="70c" wo="17.94" />
<nuclide name="Zr-96" xs="70c" wo="2.73" />
<density value="6.44" units="g/cc" />
<nuclide name="O16" xs="70c" wo="0.125" />
<nuclide name="Cr50" xs="70c" wo="0.004345" />
<nuclide name="Cr52" xs="70c" wo="0.083789" />
<nuclide name="Cr53" xs="70c" wo="0.009501" />
<nuclide name="Cr54" xs="70c" wo="0.002365" />
<nuclide name="Sn112" xs="70c" wo="0.014065" />
<nuclide name="Sn114" xs="70c" wo="0.00957" />
<nuclide name="Sn115" xs="70c" wo="0.00493" />
<nuclide name="Sn116" xs="70c" wo="0.21083" />
<nuclide name="Sn117" xs="70c" wo="0.11136" />
<nuclide name="Sn118" xs="70c" wo="0.35119" />
<nuclide name="Sn119" xs="70c" wo="0.124555" />
<nuclide name="Sn120" xs="70c" wo="0.47241" />
<nuclide name="Sn122" xs="70c" wo="0.067135" />
<nuclide name="Sn124" xs="70c" wo="0.083955" />
<nuclide name="Fe54" xs="70c" wo="0.0122745" />
<nuclide name="Fe56" xs="70c" wo="0.1926834" />
<nuclide name="Fe57" xs="70c" wo="0.004431" />
<nuclide name="Fe58" xs="70c" wo="0.0005922" />
<nuclide name="Zr90" xs="70c" wo="50.16" />
<nuclide name="Zr91" xs="70c" wo="10.94" />
<nuclide name="Zr92" xs="70c" wo="16.72" />
<nuclide name="Zr94" xs="70c" wo="17.94" />
<nuclide name="Zr96" xs="70c" wo="2.73" />
</material>
<!-- Heavy water -->
<material id="7">
<density value="1.07801" units="g/cc" />
<nuclide name="O-16" xs="73c" ao="1" />
<nuclide name="H-2" xs="80c" ao="1.996" />
<nuclide name="H-1" xs="80c" ao="0.004" />
<sab name="lwtr" xs="11t" />
<sab name="hwtr" xs="11t" />
<nuclide name="O16" xs="73c" ao="1" />
<nuclide name="H2" xs="80c" ao="1.996" />
<nuclide name="H1" xs="80c" ao="0.004" />
<sab name="c_H_in_H2O" xs="11t" />
<sab name="c_D_in_D2O" xs="11t" />
</material>
</materials>

4
ARC700/CANDU 2.6/problem/settings.xml
View file

@ -10,10 +10,6 @@
====================================================
-->
<cross_sections>
/home/ahmedk/Desktop/xdata/cross_sections1.xml
</cross_sections>
<!-- Parameters for k-eigenvalue calculation -->
<eigenvalue>
<batches>600</batches>

68
ARC700/CANDU 2.6/problem/tallies.xml
View file

@ -1,47 +1,77 @@
<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>93 87</bins>
</filter>
<filter id="2" type="cell">
<bins>93 87</bins>
</filter>
<filter id="3" type="cell">
<bins>93 87</bins>
</filter>
<filter id="4" type="cell">
<bins>93 87</bins>
</filter>
<filter id="5" type="cell">
<bins>93 87</bins>
</filter>
<filter id="6" type="cell">
<bins>93 87</bins>
</filter>
<filter id="7" type="cell">
<bins>93 87</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filter type="cell" bins="93 87" />
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="93 87" />
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="93 87" />
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="93 87" />
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="93 87" />
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="93 87" />
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="93 87" />
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
<tally id="8">
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

186
ARC700/CANDU 3.1/problem/materials.xml
View file

@ -9,142 +9,144 @@
Date: 02/03/2017
====================================================
-->
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<material id="11">
<density value="9.82" units="g/cc" />
<nuclide name="U-235" xs="73c" wo="3.1" />
<nuclide name="U-238" xs="73c" wo="96.9" />
<nuclide name="O-16" xs="73c" wo="13.4529" />
<nuclide name="U235" xs="73c" wo="3.1" />
<nuclide name="U238" xs="73c" wo="96.9" />
<nuclide name="O16" xs="73c" wo="13.4529" />
</material>
<material id="12">
<density value="9.82" units="g/cc" />
<nuclide name="U-235" xs="72c" wo="3.1" />
<nuclide name="U-238" xs="72c" wo="96.9" />
<nuclide name="O-16" xs="72c" wo="13.4529" />
<nuclide name="U235" xs="72c" wo="3.1" />
<nuclide name="U238" xs="72c" wo="96.9" />
<nuclide name="O16" xs="72c" wo="13.4529" />
</material>
<material id="13">
<density value="10.298" units="g/cc" />
<nuclide name="U-235" xs="72c" wo="3.1" />
<nuclide name="U-238" xs="72c" wo="96.9" />
<nuclide name="U235" xs="72c" wo="3.1" />
<nuclide name="U238" xs="72c" wo="96.9" />
<nuclide name="O-16" xs="72c" wo="13.4529" />
</material>
<material id="14">
<density value="10.298" units="g/cc" />
<nuclide name="U-235" xs="72c" wo="0.72" />
<nuclide name="U-238" xs="72c" wo="99.28" />
<nuclide name="O-16" xs="72c" wo="13.4529" />
<nuclide name="Dy-160" xs="72c" wo="0.1735" />
<nuclide name="Dy-161" xs="72c" wo="1.418" />
<nuclide name="Dy-162" xs="72c" wo="1.915" />
<nuclide name="Dy-163" xs="72c" wo="1.861" />
<nuclide name="Dy-164" xs="72c" wo="2.1317" />
<nuclide name="U235" xs="72c" wo="0.72" />
<nuclide name="U238" xs="72c" wo="99.28" />
<nuclide name="O16" xs="72c" wo="13.4529" />
<nuclide name="Dy160" xs="72c" wo="0.1735" />
<nuclide name="Dy161" xs="72c" wo="1.418" />
<nuclide name="Dy162" xs="72c" wo="1.915" />
<nuclide name="Dy163" xs="72c" wo="1.861" />
<nuclide name="Dy164" xs="72c" wo="2.1317" />
</material>
<!-- Zircaloy 4 -->
<material id="2">
<density value="7.48" units="g/cc" />
<nuclide name="O-16" xs="71c" wo="0.125" />
<nuclide name="Cr-50" xs="71c" wo="0.004345" />
<nuclide name="Cr-52" xs="71c" wo="0.083789" />
<nuclide name="Cr-53" xs="71c" wo="0.009501" />
<nuclide name="Cr-54" xs="71c" wo="0.002365" />
<nuclide name="Sn-112" xs="71c" wo="0.014065" />
<nuclide name="Sn-114" xs="71c" wo="0.00957" />
<nuclide name="Sn-115" xs="71c" wo="0.00493" />
<nuclide name="Sn-116" xs="71c" wo="0.21083" />
<nuclide name="Sn-117" xs="71c" wo="0.11136" />
<nuclide name="Sn-118" xs="71c" wo="0.35119" />
<nuclide name="Sn-119" xs="71c" wo="0.124555" />
<nuclide name="Sn-120" xs="71c" wo="0.47241" />
<nuclide name="Sn-122" xs="71c" wo="0.067135" />
<nuclide name="Sn-124" xs="71c" wo="0.083955" />
<nuclide name="Fe-54" xs="71c" wo="0.0122745" />
<nuclide name="Fe-56" xs="71c" wo="0.1926834" />
<nuclide name="Fe-57" xs="71c" wo="0.0044499" />
<nuclide name="Fe-58" xs="71c" wo="0.0005922" />
<nuclide name="Zr-90" xs="71c" wo="50.48" />
<nuclide name="Zr-91" xs="71c" wo="11" />
<nuclide name="Zr-92" xs="71c" wo="16.83" />
<nuclide name="Zr-94" xs="71c" wo="17.05" />
<nuclide name="Zr-96" xs="71c" wo="2.75" />
<nuclide name="O16" xs="71c" wo="0.125" />
<nuclide name="Cr50" xs="71c" wo="0.004345" />
<nuclide name="Cr52" xs="71c" wo="0.083789" />
<nuclide name="Cr53" xs="71c" wo="0.009501" />
<nuclide name="Cr54" xs="71c" wo="0.002365" />
<nuclide name="Sn112" xs="71c" wo="0.014065" />
<nuclide name="Sn114" xs="71c" wo="0.00957" />
<nuclide name="Sn115" xs="71c" wo="0.00493" />
<nuclide name="Sn116" xs="71c" wo="0.21083" />
<nuclide name="Sn117" xs="71c" wo="0.11136" />
<nuclide name="Sn118" xs="71c" wo="0.35119" />
<nuclide name="Sn119" xs="71c" wo="0.124555" />
<nuclide name="Sn120" xs="71c" wo="0.47241" />
<nuclide name="Sn122" xs="71c" wo="0.067135" />
<nuclide name="Sn124" xs="71c" wo="0.083955" />
<nuclide name="Fe54" xs="71c" wo="0.0122745" />
<nuclide name="Fe56" xs="71c" wo="0.1926834" />
<nuclide name="Fe57" xs="71c" wo="0.0044499" />
<nuclide name="Fe58" xs="71c" wo="0.0005922" />
<nuclide name="Zr90" xs="71c" wo="50.48" />
<nuclide name="Zr91" xs="71c" wo="11" />
<nuclide name="Zr92" xs="71c" wo="16.83" />
<nuclide name="Zr94" xs="71c" wo="17.05" />
<nuclide name="Zr96" xs="71c" wo="2.75" />
</material>
<!-- water -->
<material id="3">
<density value="0.71273" units="g/cc" />
<nuclide name="H-1" ao="0.6666" />
<nuclide name="O-16" ao="0.3334" />
<sab name="lwtr" xs="15t" />
<nuclide name="H1" ao="0.6666" />
<nuclide name="O16" ao="0.3334" />
<sab name="c_H_in_H2O" xs="15t" />
</material>
<!-- pressure tubr zr + Nb-->
<material id="4">
<density value="6.57" units="g/cc" />
<nuclide name="Zr-90" xs="71c" wo="50.16" />
<nuclide name="Zr-91" xs="71c" wo="10.94" />
<nuclide name="Zr-92" xs="71c" wo="16.72" />
<nuclide name="Zr-94" xs="71c" wo="16.945" />
<nuclide name="Zr-96" xs="71c" wo="2.73" />
<nuclide name="Nb-93" xs="71c" wo="2.5" />
<nuclide name="Zr90" xs="71c" wo="50.16" />
<nuclide name="Zr91" xs="71c" wo="10.94" />
<nuclide name="Zr92" xs="71c" wo="16.72" />
<nuclide name="Zr94" xs="71c" wo="16.945" />
<nuclide name="Zr96" xs="71c" wo="2.73" />
<nuclide name="Nb93" xs="71c" wo="2.5" />
</material>
<!-- grph -->
<material id="5">
<density value="0.0017" units="g/cc" />
<nuclide name="O-16" ao="0.6666" />
<nuclide name="C-Nat" ao="0.3334" />
<sab name="grph" xs="11t" />
<nuclide name="O16" ao="0.6666" />
<nuclide name="CNat" ao="0.3334" />
<sab name="c_Graphite" xs="11t" />
</material>
<!--Calandria Zirconium alloy grade R60804 -->
<material id="6">
<density value="6.44" units="g/cc" />
<nuclide name="O-16" xs="70c" wo="0.125" />
<nuclide name="Cr-50" xs="70c" wo="0.004345" />
<nuclide name="Cr-52" xs="70c" wo="0.083789" />
<nuclide name="Cr-53" xs="70c" wo="0.009501" />
<nuclide name="Cr-54" xs="70c" wo="0.002365" />
<nuclide name="Sn-112" xs="70c" wo="0.014065" />
<nuclide name="Sn-114" xs="70c" wo="0.00957" />
<nuclide name="Sn-115" xs="70c" wo="0.00493" />
<nuclide name="Sn-116" xs="70c" wo="0.21083" />
<nuclide name="Sn-117" xs="70c" wo="0.11136" />
<nuclide name="Sn-118" xs="70c" wo="0.35119" />
<nuclide name="Sn-119" xs="70c" wo="0.124555" />
<nuclide name="Sn-120" xs="70c" wo="0.47241" />
<nuclide name="Sn-122" xs="70c" wo="0.067135" />
<nuclide name="Sn-124" xs="70c" wo="0.083955" />
<nuclide name="Fe-54" xs="70c" wo="0.0122745" />
<nuclide name="Fe-56" xs="70c" wo="0.1926834" />
<nuclide name="Fe-57" xs="70c" wo="0.004431" />
<nuclide name="Fe-58" xs="70c" wo="0.0005922" />
<nuclide name="Zr-90" xs="70c" wo="50.16" />
<nuclide name="Zr-91" xs="70c" wo="10.94" />
<nuclide name="Zr-92" xs="70c" wo="16.72" />
<nuclide name="Zr-94" xs="70c" wo="17.94" />
<nuclide name="Zr-96" xs="70c" wo="2.73" />
<density value="6.44" units="g/cc" />
<nuclide name="O16" xs="70c" wo="0.125" />
<nuclide name="Cr50" xs="70c" wo="0.004345" />
<nuclide name="Cr52" xs="70c" wo="0.083789" />
<nuclide name="Cr53" xs="70c" wo="0.009501" />
<nuclide name="Cr54" xs="70c" wo="0.002365" />
<nuclide name="Sn112" xs="70c" wo="0.014065" />
<nuclide name="Sn114" xs="70c" wo="0.00957" />
<nuclide name="Sn115" xs="70c" wo="0.00493" />
<nuclide name="Sn116" xs="70c" wo="0.21083" />
<nuclide name="Sn117" xs="70c" wo="0.11136" />
<nuclide name="Sn118" xs="70c" wo="0.35119" />
<nuclide name="Sn119" xs="70c" wo="0.124555" />
<nuclide name="Sn120" xs="70c" wo="0.47241" />
<nuclide name="Sn122" xs="70c" wo="0.067135" />
<nuclide name="Sn124" xs="70c" wo="0.083955" />
<nuclide name="Fe54" xs="70c" wo="0.0122745" />
<nuclide name="Fe56" xs="70c" wo="0.1926834" />
<nuclide name="Fe57" xs="70c" wo="0.004431" />
<nuclide name="Fe58" xs="70c" wo="0.0005922" />
<nuclide name="Zr90" xs="70c" wo="50.16" />
<nuclide name="Zr91" xs="70c" wo="10.94" />
<nuclide name="Zr92" xs="70c" wo="16.72" />
<nuclide name="Zr94" xs="70c" wo="17.94" />
<nuclide name="Zr96" xs="70c" wo="2.73" />
</material>
<!-- Heavy water -->
<material id="7">
<density value="1.07801" units="g/cc" />
<nuclide name="O-16" xs="73c" ao="1" />
<nuclide name="H-2" xs="80c" ao="1.996" />
<nuclide name="H-1" xs="80c" ao="0.004" />
<sab name="lwtr" xs="11t" />
<sab name="hwtr" xs="11t" />
<nuclide name="O16" xs="73c" ao="1" />
<nuclide name="H2" xs="80c" ao="1.996" />
<nuclide name="H1" xs="80c" ao="0.004" />
<sab name="c_H_in_H2O" xs="11t" />
<sab name="c_D_in_D2O" xs="11t" />
</material>
</materials>

4
ARC700/CANDU 3.1/problem/settings.xml
View file

@ -10,10 +10,6 @@
====================================================
-->
<cross_sections>
/home/ahmedk/Desktop/xdata/cross_sections1.xml
</cross_sections>
<!-- Parameters for k-eigenvalue calculation -->
<eigenvalue>
<batches>600</batches>

68
ARC700/CANDU 3.1/problem/tallies.xml
View file

@ -1,47 +1,77 @@
<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>93 87</bins>
</filter>
<filter id="2" type="cell">
<bins>93 87</bins>
</filter>
<filter id="3" type="cell">
<bins>93 87</bins>
</filter>
<filter id="4" type="cell">
<bins>93 87</bins>
</filter>
<filter id="5" type="cell">
<bins>93 87</bins>
</filter>
<filter id="6" type="cell">
<bins>93 87</bins>
</filter>
<filter id="7" type="cell">
<bins>93 87</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filter type="cell" bins="93 87" />
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="93 87" />
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="93 87" />
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="93 87" />
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="93 87" />
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="93 87" />
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="93 87" />
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
<tally id="8">
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

101
VVER/VVER 2.1/problem/materials.xml
View file

@ -1,5 +1,5 @@
<?xml version='1.0' encoding='utf-8'?>
<materials>
<!--
====================================================
@ -9,76 +9,77 @@
Date: 02/03/2017
====================================================
-->
<materials>
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 2.1% -->
<material id="1">
<density value="10.55" units="g/cc" />
<nuclide name="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" />
<nuclide name="U235" xs="80c" wo="0.0185105302348" />
<nuclide name="U238" xs="80c" wo="0.862943290471" />
<nuclide name="O16" xs="80c" wo="0.118546179294" />
</material>
<!-- 3.6% UO2 + 5% Gd2O3 -->
<material id="5">
<density value="10.547" units="g/cc" />
<nuclide name="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 " />
<nuclide name="U235" xs="80c" wo="0.0292792" />
<nuclide name="U238" xs="80c" wo="0.7940422" />
<nuclide name="O16" xs="80c" wo="0.1194922" />
<nuclide name="Gd157" xs="80c" wo="0.0571954 " />
</material>
<!-- Cladding material alloy Э110 -->
<material id="2">
<density value="6.4516" units="g/cc" />
<nuclide name="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" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Hf174" xs="80c" wo="0.00000048" />
<nuclide name="Hf176" xs="80c" wo="0.00001578" />
<nuclide name="Hf177" xs="80c" wo="0.0000558" />
<nuclide name="Hf178" xs="80c" wo="0.00008184" />
<nuclide name="Hf179" xs="80c" wo="0.00004086" />
<nuclide name="Hf180" xs="80c" wo="0.00010524" />
<nuclide name="Zr90" xs="80c" wo="0.50920065" />
<nuclide name="Zr91" xs="80c" wo="0.11104434" />
<nuclide name="Zr92" xs="80c" wo="0.16973355" />
<nuclide name="Zr94" xs="80c" wo="0.17200986" />
<nuclide name="Zr96" xs="80c" wo="0.0277116" />
</material>
<!-- Water -->
<material id="3">
<density value="0.716" units="g/cc" />
<nuclide name="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" />
<nuclide name="H1" xs="80c" wo="0.06312" />
<nuclide name="O16" xs="80c" wo="0.13539" />
<nuclide name="B11" xs="80c" wo="0.80149" />
</material>
<!-- Guide Tube alloy Э635 -->
<material id="4">
<density value="6.55" units="g/cc" />
<nuclide name="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" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Sn112" xs="80c" wo="0.0001261" />
<nuclide name="Sn114" xs="80c" wo="0.0000858" />
<nuclide name="Sn115" xs="80c" wo="0.0000442" />
<nuclide name="Sn116" xs="80c" wo="0.0018902" />
<nuclide name="Sn117" xs="80c" wo="0.0009984" />
<nuclide name="Sn118" xs="80c" wo="0.0031486" />
<nuclide name="Sn119" xs="80c" wo="0.0011167" />
<nuclide name="Sn120" xs="80c" wo="0.0042354" />
<nuclide name="Sn122" xs="80c" wo="0.0006019" />
<nuclide name="Sn124" xs="80c" wo="0.0007527" />
<nuclide name="Fe54" xs="80c" wo="0.00017535" />
<nuclide name="Fe56" xs="80c" wo="0.00275262" />
<nuclide name="Fe57" xs="80c" wo="0.00006357" />
<nuclide name="Fe58" xs="80c" wo="0.00000846" />
<nuclide name="Zr90" xs="80c" wo="0.50662815" />
<nuclide name="Zr91" xs="80c" wo="0.11048334" />
<nuclide name="Zr92" xs="80c" wo="0.16887605" />
<nuclide name="Zr94" xs="80c" wo="0.17114086" />
<nuclide name="Zr96" xs="80c" wo="0.0275716" />
</material>
</materials>

4
VVER/VVER 2.1/problem/settings.xml
View file

@ -9,10 +9,6 @@
Date: 02/03/2017
====================================================
-->
<cross_sections>
/home/ahmedk/Desktop/xdata/cross_sections1.xml
</cross_sections>
<eigenvalue>
<batches>600</batches>

68
VVER/VVER 2.1/problem/tallies.xml
View file

@ -1,47 +1,77 @@
<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>1</bins>
</filter>
<filter id="3" type="cell">
<bins>1</bins>
</filter>
<filter id="4" type="cell">
<bins>1</bins>
</filter>
<filter id="5" type="cell">
<bins>1</bins>
</filter>
<filter id="6" type="cell">
<bins>1</bins>
</filter>
<filter id="7" type="cell">
<bins>1</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filter type="cell" bins="1" />
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="1" />
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="1" />
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="1" />
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="1" />
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="1" />
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
<tally id="8">
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

101
VVER/VVER 2.6/problem/materials.xml
View file

@ -1,5 +1,5 @@
<?xml version='1.0' encoding='utf-8'?>
<materials>
<!--
====================================================
@ -9,76 +9,77 @@
Date: 02/03/2017
====================================================
-->
<materials>
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 2.6% -->
<material id="1">
<density value="10.55" units="g/cc" />
<nuclide name="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" />
<nuclide name="U235" xs="80c" wo="0.0229176280555" />
<nuclide name="U238" xs="80c" wo="0.858529604849" />
<nuclide name="O16" xs="80c" wo="0.118552767096" />
</material>
<!-- 3.6% UO2 + 5% Gd2O3 -->
<material id="5">
<density value="10.547" units="g/cc" />
<nuclide name="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 " />
<nuclide name="U235" xs="80c" wo="0.0292792" />
<nuclide name="U238" xs="80c" wo="0.7940422" />
<nuclide name="O16" xs="80c" wo="0.1194922" />
<nuclide name="Gd157" xs="80c" wo="0.0571954 " />
</material>
<!-- Cladding material alloy Э110 -->
<material id="2">
<density value="6.4516" units="g/cc" />
<nuclide name="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" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Hf174" xs="80c" wo="0.00000048" />
<nuclide name="Hf176" xs="80c" wo="0.00001578" />
<nuclide name="Hf177" xs="80c" wo="0.0000558" />
<nuclide name="Hf178" xs="80c" wo="0.00008184" />
<nuclide name="Hf179" xs="80c" wo="0.00004086" />
<nuclide name="Hf180" xs="80c" wo="0.00010524" />
<nuclide name="Zr90" xs="80c" wo="0.50920065" />
<nuclide name="Zr91" xs="80c" wo="0.11104434" />
<nuclide name="Zr92" xs="80c" wo="0.16973355" />
<nuclide name="Zr94" xs="80c" wo="0.17200986" />
<nuclide name="Zr96" xs="80c" wo="0.0277116" />
</material>
<!-- Water -->
<material id="3">
<density value="0.716" units="g/cc" />
<nuclide name="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" />
<nuclide name="H1" xs="80c" wo="0.06312" />
<nuclide name="O16" xs="80c" wo="0.13539" />
<nuclide name="B11" xs="80c" wo="0.80149" />
</material>
<!-- Guide Tube alloy Э635 -->
<material id="4">
<density value="6.55" units="g/cc" />
<nuclide name="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" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Sn112" xs="80c" wo="0.0001261" />
<nuclide name="Sn114" xs="80c" wo="0.0000858" />
<nuclide name="Sn115" xs="80c" wo="0.0000442" />
<nuclide name="Sn116" xs="80c" wo="0.0018902" />
<nuclide name="Sn117" xs="80c" wo="0.0009984" />
<nuclide name="Sn118" xs="80c" wo="0.0031486" />
<nuclide name="Sn119" xs="80c" wo="0.0011167" />
<nuclide name="Sn120" xs="80c" wo="0.0042354" />
<nuclide name="Sn122" xs="80c" wo="0.0006019" />
<nuclide name="Sn124" xs="80c" wo="0.0007527" />
<nuclide name="Fe54" xs="80c" wo="0.00017535" />
<nuclide name="Fe56" xs="80c" wo="0.00275262" />
<nuclide name="Fe57" xs="80c" wo="0.00006357" />
<nuclide name="Fe58" xs="80c" wo="0.00000846" />
<nuclide name="Zr90" xs="80c" wo="0.50662815" />
<nuclide name="Zr91" xs="80c" wo="0.11048334" />
<nuclide name="Zr92" xs="80c" wo="0.16887605" />
<nuclide name="Zr94" xs="80c" wo="0.17114086" />
<nuclide name="Zr96" xs="80c" wo="0.0275716" />
</material>
</materials>

4
VVER/VVER 2.6/problem/settings.xml
View file

@ -10,10 +10,6 @@
====================================================
-->
<cross_sections>
/home/ahmedk/Desktop/xdata/cross_sections1.xml
</cross_sections>
<eigenvalue>
<batches>600</batches>
<inactive>50</inactive>

67
VVER/VVER 2.6/problem/tallies.xml
View file

@ -1,46 +1,77 @@
<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>1</bins>
</filter>
<filter id="3" type="cell">
<bins>1</bins>
</filter>
<filter id="4" type="cell">
<bins>1</bins>
</filter>
<filter id="5" type="cell">
<bins>1</bins>
</filter>
<filter id="6" type="cell">
<bins>1</bins>
</filter>
<filter id="7" type="cell">
<bins>1</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filter type="cell" bins="1" />
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="1" />
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="1" />
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="1" />
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="1" />
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="1" />
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>

101
VVER/VVER 3.6/problem/materials.xml
View file

@ -1,5 +1,5 @@
<?xml version='1.0' encoding='utf-8'?>
<materials>
<!--
====================================================
@ -9,76 +9,77 @@
Date: 02/03/2017
====================================================
-->
<materials>
<cross_sections>/opt/xdata/endfb-vii.1-hdf5/cross_sections.xml</cross_sections>
<default_xs>71c</default_xs>
<!-- Fuel composed of U-238 O-16 and U-235 3.7% -->
<material id="1">
<density value="10.55" units="g/cc" />
<nuclide name="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" />
<nuclide name="U235" xs="80c" wo="0.03221694" />
<nuclide name="U238" xs="80c" wo="0.84921578" />
<nuclide name="O16" xs="80c" wo="0.11856726" />
</material>
<!-- 3.6% UO2 + 5% Gd2O3 -->
<material id="5">
<density value="10.547" units="g/cc" />
<nuclide name="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 " />
<nuclide name="U235" xs="80c" wo="0.0292792" />
<nuclide name="U238" xs="80c" wo="0.7940422" />
<nuclide name="O16" xs="80c" wo="0.1194922" />
<nuclide name="Gd157" xs="80c" wo="0.0571954 " />
</material>
<!-- Cladding material alloy Э110 -->
<material id="2">
<density value="6.4516" units="g/cc" />
<nuclide name="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" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Hf174" xs="80c" wo="0.00000048" />
<nuclide name="Hf176" xs="80c" wo="0.00001578" />
<nuclide name="Hf177" xs="80c" wo="0.0000558" />
<nuclide name="Hf178" xs="80c" wo="0.00008184" />
<nuclide name="Hf179" xs="80c" wo="0.00004086" />
<nuclide name="Hf180" xs="80c" wo="0.00010524" />
<nuclide name="Zr90" xs="80c" wo="0.50920065" />
<nuclide name="Zr91" xs="80c" wo="0.11104434" />
<nuclide name="Zr92" xs="80c" wo="0.16973355" />
<nuclide name="Zr94" xs="80c" wo="0.17200986" />
<nuclide name="Zr96" xs="80c" wo="0.0277116" />
</material>
<!-- Water -->
<material id="3">
<density value="0.716" units="g/cc" />
<nuclide name="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" />
<nuclide name="H1" xs="80c" wo="0.06312" />
<nuclide name="O16" xs="80c" wo="0.13539" />
<nuclide name="B11" xs="80c" wo="0.80149" />
</material>
<!-- Guide Tube alloy Э635 -->
<material id="4">
<density value="6.55" units="g/cc" />
<nuclide name="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" />
<nuclide name="Nb93" xs="80c" wo="0.0100" />
<nuclide name="Sn112" xs="80c" wo="0.0001261" />
<nuclide name="Sn114" xs="80c" wo="0.0000858" />
<nuclide name="Sn115" xs="80c" wo="0.0000442" />
<nuclide name="Sn116" xs="80c" wo="0.0018902" />
<nuclide name="Sn117" xs="80c" wo="0.0009984" />
<nuclide name="Sn118" xs="80c" wo="0.0031486" />
<nuclide name="Sn119" xs="80c" wo="0.0011167" />
<nuclide name="Sn120" xs="80c" wo="0.0042354" />
<nuclide name="Sn122" xs="80c" wo="0.0006019" />
<nuclide name="Sn124" xs="80c" wo="0.0007527" />
<nuclide name="Fe54" xs="80c" wo="0.00017535" />
<nuclide name="Fe56" xs="80c" wo="0.00275262" />
<nuclide name="Fe57" xs="80c" wo="0.00006357" />
<nuclide name="Fe58" xs="80c" wo="0.00000846" />
<nuclide name="Zr90" xs="80c" wo="0.50662815" />
<nuclide name="Zr91" xs="80c" wo="0.11048334" />
<nuclide name="Zr92" xs="80c" wo="0.16887605" />
<nuclide name="Zr94" xs="80c" wo="0.17114086" />
<nuclide name="Zr96" xs="80c" wo="0.0275716" />
</material>
</materials>

5
VVER/VVER 3.6/problem/settings.xml
View file

@ -10,11 +10,6 @@
====================================================
-->
<cross_sections>
/home/ahmedk/Desktop/xdata/cross_sections1.xml
</cross_sections>
<eigenvalue>
<batches>600</batches>
<inactive>50</inactive>

67
VVER/VVER 3.6/problem/tallies.xml
View file

@ -1,46 +1,77 @@
<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>1</bins>
</filter>
<filter id="2" type="cell">
<bins>1</bins>
</filter>
<filter id="3" type="cell">
<bins>1</bins>
</filter>
<filter id="4" type="cell">
<bins>1</bins>
</filter>
<filter id="5" type="cell">
<bins>1</bins>
</filter>
<filter id="6" type="cell">
<bins>1</bins>
</filter>
<filter id="7" type="cell">
<bins>1</bins>
</filter>
<filter id="8" type="delayedgroup">
<bins>1 2 3 4 5 6</bins>
</filter>
<tally id="1">
<filter type="cell" bins="1" />
<filters>1</filters>
<scores>flux</scores>
</tally>
<tally id="2">
<filter type="cell" bins="1" />
<filters>2</filters>
<scores>nu-fission</scores>
</tally>
<tally id="3">
<filter type="cell" bins="1" />
<filters>3</filters>
<scores>delayed-nu-fission</scores>
</tally>
<tally id="4">
<filter type="cell" bins="1" />
<tally id="4">
<filters>4</filters>
<scores>fission</scores>
</tally>
<tally id="5">
<filter type="cell" bins="1" />
<filters>5</filters>
<scores>absorption</scores>
</tally>
<tally id="6">
<filter type="cell" bins="1" />
<filters>6</filters>
<scores>scatter</scores>
</tally>
<tally id="7">
<filter type="cell" bins="1" />
<filters>7</filters>
<scores>total</scores>
</tally>
<tally id="8">
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
<scores>delayed-nu-fission</scores>
<filters>8</filters>
<scores>delayed-nu-fission</scores>
</tally>
</tallies>