update old tests to use new model.xml

This commit is contained in:
Ethan Peterson 2023-03-23 14:59:37 -04:00
parent 7200d42644
commit 04806858ca
66 changed files with 1241 additions and 1787 deletions

View file

@ -683,11 +683,11 @@ class Plot(IDManagerMixin):
if self._meshlines is not None:
subelement = ET.SubElement(element, "meshlines")
subelement.set("meshtype", self._meshlines['type'])
if self._meshlines['id'] is not None:
if 'id' in self._meshlines:
subelement.set("id", str(self._meshlines['id']))
if self._meshlines['linewidth'] is not None:
if 'linewidth' in self._meshlines:
subelement.set("linewidth", str(self._meshlines['linewidth']))
if self._meshlines['color'] is not None:
if 'color' in self._meshlines:
subelement.set("color", ' '.join(map(
str, self._meshlines['color'])))

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
<type>z-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

View file

@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
</mesh>
<entropy_mesh>10</entropy_mesh>
</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
<type>z-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

View file

@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
</mesh>
<entropy_mesh>10</entropy_mesh>
</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
<type>z-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

View file

@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
</mesh>
<entropy_mesh>10</entropy_mesh>
</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
<type>z-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

View file

@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
</mesh>
<entropy_mesh>10</entropy_mesh>
</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

View file

@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
<type>z-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
</geometry>

View file

@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

View file

@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

View file

@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
</mesh>
<entropy_mesh>10</entropy_mesh>
</settings>

View file

@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

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@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
<type>z-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
</geometry>

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@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

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@ -0,0 +1,51 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

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@ -1,26 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
</mesh>
<entropy_mesh>10</entropy_mesh>
</settings>

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@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

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@ -1,43 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<region>-1 2 -3 4 -5 6</region>
<material>1</material>
</cell>
<!-- Defition of Surfaces -->
<surface id="1">
<type>x-plane</type>
<coeffs>10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="2">
<type>x-plane</type>
<coeffs>-10</coeffs>
<boundary> vacuum </boundary>
</surface>
<surface id="3">
<type>y-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="4">
<type>y-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="5">
<type>z-plane</type>
<coeffs>1</coeffs>
<boundary>reflective</boundary>
</surface>
<surface id="6">
<type>z-plane</type>
<coeffs>-1</coeffs>
<boundary>reflective</boundary>
</surface>
</geometry>

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@ -1,12 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="19" units="g/cc" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>

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@ -0,0 +1,54 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="19.0" />
<nuclide name="U235" wo="0.21" />
<nuclide name="U238" wo="0.68" />
<nuclide name="O16" wo="0.11" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 2 -3 4 -5 6" universe="0" />
<surface boundary="vacuum" coeffs="10.0" id="1" type="x-plane" />
<surface boundary="vacuum" coeffs="-10.0" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="1.0" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="-1.0" id="4" type="y-plane" />
<surface boundary="reflective" coeffs="1.0" id="5" type="z-plane" />
<surface boundary="reflective" coeffs="-1.0" id="6" type="z-plane" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>20</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-10.0 -1.0 -1.0 10.0 1.0 1.0</parameters>
</space>
</source>
<state_point>
<batches>15 20</batches>
</state_point>
<entropy_mesh>10</entropy_mesh>
<mesh id="10">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="1">
<dimension>10 1 1</dimension>
<lower_left>-10.0 -1.0 -1.0</lower_left>
<upper_right>10.0 1.0 1.0</upper_right>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>
</model>

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@ -1,28 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- Starting source -->
<source>
<space>
<type>box</type>
<parameters>-10 -1 -1 10 1 1</parameters>
</space>
</source>
<!-- Shannon Entropy -->
<mesh id="10">
<dimension> 10 1 1 </dimension>
<lower_left> -10.0 -1.0 -1.0 </lower_left>
<upper_right> 10.0 1.0 1.0 </upper_right>
</mesh>
<entropy_mesh>10</entropy_mesh>
<state_point batches="15 20" />
</settings>

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@ -1,21 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<lower_left>-10 -1 -1 </lower_left>
<upper_right>10 1 1</upper_right>
<dimension>10 1 1</dimension>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>flux</scores>
</tally>
</tallies>

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@ -1,23 +0,0 @@
<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell fill="5" id="1" name="Cell 1" region="1 -2 3 -4" universe="0" />
<cell id="101" material="1" name="cell 2" region="-5" universe="1" />
<cell id="102" material="2" name="cell 3" region="5" universe="1" />
<cell id="500" material="2" name="cell 4" region="" universe="3" />
<hex_lattice id="5" n_rings="2">
<pitch>1.0</pitch>
<outer>3</outer>
<center>0.0 0.0</center>
<universes>
1
1 1
1
1 1
1</universes>
</hex_lattice>
<surface boundary="vacuum" coeffs="-3" id="1" name="left" type="x-plane" />
<surface boundary="vacuum" coeffs="3" id="2" name="right" type="x-plane" />
<surface boundary="vacuum" coeffs="-4" id="3" name="bottom" type="y-plane" />
<surface boundary="vacuum" coeffs="4" id="4" name="top" type="y-plane" />
<surface boundary="transmission" coeffs="0 0 0.4" id="5" type="z-cylinder" />
</geometry>

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@ -1,19 +0,0 @@
<?xml version='1.0' encoding='utf-8'?>
<materials>
<material id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="moderator">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="2.0" name="H1" />
<sab name="c_H_in_H2O" />
</material>
<material id="3" name="iron">
<density units="g/cc" value="7.9" />
<nuclide ao="1.0" name="Fe56" />
</material>
</materials>

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@ -0,0 +1,61 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1" name="fuel">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material id="2" name="moderator">
<density units="g/cc" value="1.0" />
<nuclide ao="1.0" name="O16" />
<nuclide ao="2.0" name="H1" />
<sab name="c_H_in_H2O" />
</material>
<material id="3" name="iron">
<density units="g/cc" value="7.9" />
<nuclide ao="1.0" name="Fe56" />
</material>
</materials>
<geometry>
<cell fill="5" id="1" name="Cell 1" region="1 -2 3 -4" universe="0" />
<cell id="101" material="1" name="cell 2" region="-5" universe="1" />
<cell id="102" material="2" name="cell 3" region="5" universe="1" />
<cell id="500" material="2" name="cell 4" universe="3" />
<hex_lattice id="5" n_rings="2">
<pitch>1.0</pitch>
<outer>3</outer>
<center>0.0 0.0</center>
<universes>
1
1 1
1
1 1
1</universes>
</hex_lattice>
<surface boundary="vacuum" coeffs="-3.0" id="1" name="left" type="x-plane" />
<surface boundary="vacuum" coeffs="3.0" id="2" name="right" type="x-plane" />
<surface boundary="vacuum" coeffs="-4.0" id="3" name="bottom" type="y-plane" />
<surface boundary="vacuum" coeffs="4.0" id="4" name="top" type="y-plane" />
<surface coeffs="0.0 0.0 0.4" id="5" type="z-cylinder" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>1</batches>
<inactive>0</inactive>
<source strength="1.0">
<space type="box">
<parameters>-1.0 -1.0 -1.0 1.0 1.0 1.0</parameters>
</space>
</source>
</settings>
<tallies>
<filter id="1" type="distribcell">
<bins>101</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
</model>

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@ -1,12 +0,0 @@
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>1</batches>
<inactive>0</inactive>
<source>
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
</settings>

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@ -1,14 +0,0 @@
<?xml version='1.0' encoding='utf-8'?>
<tallies>
<filter id="1">
<type>distribcell</type>
<bins>101</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>

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@ -1,17 +0,0 @@
<?xml version="1.0"?>
<geometry>
<cell id="11" universe="11" material="1"/>
<cell id="12" universe="12" material="2" region=""/>
<lattice id="21" dimension="2 2" lower_left="-2.0 -2.0"
pitch="2.0 2.0" outer="12">
<universes>
11 12
12 11
</universes>
</lattice>
<surface id="101" type="z-cylinder" coeffs="0.0 0.0 5.0" boundary="vacuum"/>
<cell id="101" universe="0" fill="21" region="-101"/>
</geometry>

View file

@ -1,14 +0,0 @@
<?xml version="1.0"?>
<materials>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="2">
<density value="4.5" units="g/cc" />
<nuclide name="U238" ao="1.0" />
</material>
</materials>

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@ -0,0 +1,39 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U238" />
</material>
</materials>
<geometry>
<cell id="11" material="1" universe="11" />
<cell id="12" material="2" universe="12" />
<cell fill="21" id="101" region="-101" universe="0" />
<lattice id="21">
<pitch>2.0 2.0</pitch>
<outer>12</outer>
<dimension>2 2</dimension>
<lower_left>-2.0 -2.0</lower_left>
<universes>
11 12
12 11 </universes>
</lattice>
<surface boundary="vacuum" coeffs="0.0 0.0 5.0" id="101" type="z-cylinder" />
</geometry>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>10</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="box">
<parameters>-4.0 -4.0 -4.0 4.0 4.0 4.0</parameters>
</space>
</source>
</settings>
</model>

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@ -1,15 +0,0 @@
<?xml version="1.0"?>
<settings>
<run_mode>eigenvalue</run_mode>
<batches>10</batches>
<inactive>5</inactive>
<particles>1000</particles>
<source>
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>

View file

@ -1,297 +1,296 @@
import openmc
import numpy as np
names = ['H', 'O', 'Zr', 'U235', 'U238']
def build_openmc_xs_lib(name, groups, temperatures, xsdict, micro=True):
"""Build an Openm XSdata based on dictionary values"""
xsdata = openmc.XSdata(name, groups, temperatures=temperatures)
xsdata.order = 0
for tt in temperatures:
xsdata.set_absorption(xsdict[tt]['absorption'][name], temperature=tt)
xsdata.set_scatter_matrix(xsdict[tt]['scatter'][name], temperature=tt)
xsdata.set_total(xsdict[tt]['total'][name], temperature=tt)
if (name in xsdict[tt]['nu-fission'].keys()):
xsdata.set_nu_fission(xsdict[tt]['nu-fission'][name],
temperature=tt)
xsdata.set_chi(np.array([1., 0.]), temperature=tt)
return xsdata
def create_micro_xs_dict():
"""Returns micro xs library"""
xs_micro = {}
reactions = ['absorption', 'total', 'scatter', 'nu-fission']
# chi is unnecessary when energy bound is in thermal region
# Temperature 300K
# absorption
xs_micro[300] = {r: {} for r in reactions}
xs_micro[300]['absorption']['H'] = np.array([1.0285E-4, 0.0057])
xs_micro[300]['absorption']['O'] = np.array([7.1654E-5, 3.0283E-6])
xs_micro[300]['absorption']['Zr'] = np.array([4.5918E-5, 3.6303E-5])
xs_micro[300]['absorption']['U235'] = np.array([0.0035, 0.1040])
xs_micro[300]['absorption']['U238'] = np.array([0.0056, 0.0094])
# nu-scatter matrix
xs_micro[300]['scatter']['H'] = np.array([[[0.0910, 0.01469],
[0.0, 0.3316]]])
xs_micro[300]['scatter']['O'] = np.array([[[0.0814, 3.3235E-4],
[0.0, 0.0960]]])
xs_micro[300]['scatter']['Zr'] = np.array([[[0.0311, 2.6373E-5],
[0.0, 0.0315]]])
xs_micro[300]['scatter']['U235'] = np.array([[[0.0311, 2.6373E-5],
[0.0, 0.0315]]])
xs_micro[300]['scatter']['U238'] = np.array([[[0.0551, 2.2341E-5],
[0.0, 0.0526]]])
# nu-fission
xs_micro[300]['nu-fission']['U235'] = np.array([0.0059, 0.2160])
xs_micro[300]['nu-fission']['U238'] = np.array([0.0019, 1.4627E-7])
# total
xs_micro[300]['total']['H'] = xs_micro[300]['absorption']['H'] + \
np.sum(xs_micro[300]['scatter']['H'][0], 1)
xs_micro[300]['total']['O'] = xs_micro[300]['absorption']['O'] + \
np.sum(xs_micro[300]['scatter']['O'][0], 1)
xs_micro[300]['total']['Zr'] = xs_micro[300]['absorption']['Zr'] + \
np.sum(xs_micro[300]['scatter']['Zr'][0], 1)
xs_micro[300]['total']['U235'] = xs_micro[300]['absorption']['U235'] + \
np.sum(xs_micro[300]['scatter']['U235'][0], 1)
xs_micro[300]['total']['U238'] = xs_micro[300]['absorption']['U238'] + \
np.sum(xs_micro[300]['scatter']['U238'][0], 1)
# Temperature 600K
xs_micro[600] = {r: {} for r in reactions}
# absorption
xs_micro[600]['absorption']['H'] = np.array([1.0356E-4, 0.0046])
xs_micro[600]['absorption']['O'] = np.array([7.2678E-5, 2.4963E-6])
xs_micro[600]['absorption']['Zr'] = np.array([4.7256E-5, 2.9757E-5])
xs_micro[600]['absorption']['U235'] = np.array([0.0035, 0.0853])
xs_micro[600]['absorption']['U238'] = np.array([0.0058, 0.0079])
# nu-scatter matrix
xs_micro[600]['scatter']['H'] = np.array([[[0.0910, 0.0138],
[0.0, 0.3316]]])
xs_micro[600]['scatter']['O'] = np.array([[[0.0814, 3.5367E-4],
[0.0, 0.0959]]])
xs_micro[600]['scatter']['Zr'] = np.array([[[0.0311, 3.2293E-5],
[0.0, 0.0314]]])
xs_micro[600]['scatter']['U235'] = np.array([[[0.0022, 1.9763E-6],
[9.1634E-8, 0.0039]]])
xs_micro[600]['scatter']['U238'] = np.array([[[0.0556, 2.8803E-5],
[0.0, 0.0536]]])
# nu-fission
xs_micro[600]['nu-fission']['U235'] = np.array([0.0059, 0.1767])
xs_micro[600]['nu-fission']['U238'] = np.array([0.0019, 1.2405E-7])
# total
xs_micro[600]['total']['H'] = xs_micro[600]['absorption']['H'] + \
np.sum(xs_micro[600]['scatter']['H'][0], 1)
xs_micro[600]['total']['O'] = xs_micro[600]['absorption']['O'] + \
np.sum(xs_micro[600]['scatter']['O'][0], 1)
xs_micro[600]['total']['Zr'] = xs_micro[600]['absorption']['Zr'] + \
np.sum(xs_micro[600]['scatter']['Zr'][0], 1)
xs_micro[600]['total']['U235'] = xs_micro[600]['absorption']['U235'] + \
np.sum(xs_micro[600]['scatter']['U235'][0], 1)
xs_micro[600]['total']['U238'] = xs_micro[600]['absorption']['U238'] + \
np.sum(xs_micro[600]['scatter']['U238'][0], 1)
# Temperature 900K
xs_micro[900] = {r: {} for r in reactions}
# absorption
xs_micro[900]['absorption']['H'] = np.array([1.0529E-4, 0.0040])
xs_micro[900]['absorption']['O'] = np.array([7.3055E-5, 2.1850E-6])
xs_micro[900]['absorption']['Zr'] = np.array([4.7141E-5, 2.5941E-5])
xs_micro[900]['absorption']['U235'] = np.array([0.0035, 0.0749])
xs_micro[900]['absorption']['U238'] = np.array([0.0060, 0.0071])
# total
xs_micro[900]['total']['H'] = np.array([0.2982, 0.7332])
xs_micro[900]['total']['O'] = np.array([0.0885, 0.1004])
xs_micro[900]['total']['Zr'] = np.array([0.0370, 0.0317])
xs_micro[900]['total']['U235'] = np.array([0.0061, 0.0789])
xs_micro[900]['total']['U238'] = np.array([0.0707, 0.0613])
# nu-scatter matrix
xs_micro[900]['scatter']['H'] = np.array([[[0.0913, 0.0147],
[0.0, 0.4020]]])
xs_micro[900]['scatter']['O'] = np.array([[[0.0812, 4.0413E-4],
[0.0, 0.0965]]])
xs_micro[900]['scatter']['Zr'] = np.array([[[0.0311, 3.6735E-5],
[0.0, 0.0314]]])
xs_micro[900]['scatter']['U235'] = np.array([[[0.0022, 2.9034E-6],
[1.3117E-8, 0.0039]]])
xs_micro[900]['scatter']['U238'] = np.array([[[0.0560, 3.7619E-5],
[0.0, 0.0538]]])
# nu-fission
xs_micro[900]['nu-fission']['U235'] = np.array([0.0059, 0.1545])
xs_micro[900]['nu-fission']['U238'] = np.array([0.0019, 1.1017E-7])
# total
xs_micro[900]['total']['H'] = xs_micro[900]['absorption']['H'] + \
np.sum(xs_micro[900]['scatter']['H'][0], 1)
xs_micro[900]['total']['O'] = xs_micro[900]['absorption']['O'] + \
np.sum(xs_micro[900]['scatter']['O'][0], 1)
xs_micro[900]['total']['Zr'] = xs_micro[900]['absorption']['Zr'] + \
np.sum(xs_micro[900]['scatter']['Zr'][0], 1)
xs_micro[900]['total']['U235'] = xs_micro[900]['absorption']['U235'] + \
np.sum(xs_micro[900]['scatter']['U235'][0], 1)
xs_micro[900]['total']['U238'] = xs_micro[900]['absorption']['U238'] + \
np.sum(xs_micro[900]['scatter']['U238'][0], 1)
# roll axis for scatter matrix
for t in xs_micro:
for n in xs_micro[t]['scatter']:
xs_micro[t]['scatter'][n] = np.rollaxis(xs_micro[t]['scatter'][n],
0, 3)
return xs_micro
def create_macro_dict(xs_micro):
"""Create a dictionary with two group cross-section"""
xs_macro = {}
for t, d1 in xs_micro.items():
xs_macro[t] = {}
for r, d2 in d1.items():
temp = []
xs_macro[t][r] = {}
for n, v in d2.items():
temp.append(d2[n])
# The name 'macro' is needed to store data at the same level
# of a xs_macro dictionary as for xs_micro and use it in
# function build_openmc_xs_lib
xs_macro[t][r]['macro'] = sum(temp)
return xs_macro
def create_openmc_2mg_libs(names):
"""Built a micro/macro two group openmc MGXS libraries"""
# Initialized library params
group_edges = [0.0, 0.625, 20.0e6]
groups = openmc.mgxs.EnergyGroups(group_edges=group_edges)
mg_cross_sections_file_micro = openmc.MGXSLibrary(groups)
mg_cross_sections_file_macro = openmc.MGXSLibrary(groups)
# Building a micro mg library
micro_cs = create_micro_xs_dict()
for name in names:
mg_cross_sections_file_micro.add_xsdata(build_openmc_xs_lib(name,
groups,
[t for t in
micro_cs],
micro_cs))
# Building a macro mg library
macro_xs = create_macro_dict(micro_cs)
mg_cross_sections_file_macro.add_xsdata(build_openmc_xs_lib('macro',
groups,
[t for t in
macro_xs],
macro_xs))
# Exporting library to hdf5 files
mg_cross_sections_file_micro.export_to_hdf5('micro_2g.h5')
mg_cross_sections_file_macro.export_to_hdf5('macro_2g.h5')
# Returning the macro_xs dict is needed for analytical solution
return macro_xs
def analytical_solution_2g_therm(xsmin, xsmax=None, wgt=1.0):
""" Calculate eigenvalue based on analytical solution for eq Lf = (1/k)Qf
in two group for infinity dilution media in assumption of group
boundary in thermal spectra < 1.e+3 Ev
Parameters:
----------
xsmin : dict
macro cross-sections dictionary with minimum range temperature
xsmax : dict
macro cross-sections dictionary with maximum range temperature
by default: None not used for standalone temperature
wgt : float
weight for interpolation by default 1.0
Returns:
-------
keff : np.float64
analytical eigenvalue of critical eq matrix
"""
if xsmax is None:
sa = xsmin['absorption']['macro']
ss12 = xsmin['scatter']['macro'][0][1][0]
nsf = xsmin['nu-fission']['macro']
else:
sa = xsmin['absorption']['macro'] * wgt + \
xsmax['absorption']['macro'] * (1 - wgt)
ss12 = xsmin['scatter']['macro'][0][1][0] * wgt + \
xsmax['scatter']['macro'][0][1][0] * (1 - wgt)
nsf = xsmin['nu-fission']['macro'] * wgt + \
xsmax['nu-fission']['macro'] * (1 - wgt)
L = np.array([sa[0] + ss12, 0.0, -ss12, sa[1]]).reshape(2, 2)
Q = np.array([nsf[0], nsf[1], 0.0, 0.0]).reshape(2, 2)
arr = np.linalg.inv(L).dot(Q)
return np.amax(np.linalg.eigvals(arr))
def build_inf_model(xsnames, xslibname, temperature, tempmethod='nearest'):
""" Building an infinite medium for openmc multi-group testing
Parameters:
----------
xsnames : list of str()
list with xs names
xslibname:
name of hdf5 file with cross-section library
temperature : float
value of a current temperature in K
tempmethod : {'nearest', 'interpolation'}
by default 'nearest'
"""
inf_medium = openmc.Material(name='test material', material_id=1)
inf_medium.set_density("sum")
for xs in xsnames:
inf_medium.add_nuclide(xs, 1)
INF = 11.1
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([inf_medium])
materials_file.cross_sections = xslibname
materials_file.export_to_xml()
# Instantiate boundary Planes
min_x = openmc.XPlane(boundary_type='reflective', x0=-INF)
max_x = openmc.XPlane(boundary_type='reflective', x0=INF)
min_y = openmc.YPlane(boundary_type='reflective', y0=-INF)
max_y = openmc.YPlane(boundary_type='reflective', y0=INF)
# Instantiate a Cell
cell = openmc.Cell(cell_id=1, name='cell')
cell.temperature = temperature
# Register bounding Surfaces with the Cell
cell.region = +min_x & -max_x & +min_y & -max_y
# Fill the Cell with the Material
cell.fill = inf_medium
# Create root universe
root_universe = openmc.Universe(name='root universe', cells=[cell])
# Create Geometry and set root Universe
openmc_geometry = openmc.Geometry(root_universe)
# Export to "geometry.xml"
openmc_geometry.export_to_xml()
# OpenMC simulation parameters
batches = 200
inactive = 5
particles = 5000
# Instantiate a Settings object
settings_file = openmc.Settings()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.energy_mode = 'multi-group'
settings_file.output = {'summary': False}
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-INF, -INF, -INF, INF, INF, INF]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.temperature = {'method': tempmethod}
settings_file.source = openmc.Source(space=uniform_dist)
settings_file.export_to_xml()
import openmc
import numpy as np
names = ['H', 'O', 'Zr', 'U235', 'U238']
def build_openmc_xs_lib(name, groups, temperatures, xsdict, micro=True):
"""Build an Openm XSdata based on dictionary values"""
xsdata = openmc.XSdata(name, groups, temperatures=temperatures)
xsdata.order = 0
for tt in temperatures:
xsdata.set_absorption(xsdict[tt]['absorption'][name], temperature=tt)
xsdata.set_scatter_matrix(xsdict[tt]['scatter'][name], temperature=tt)
xsdata.set_total(xsdict[tt]['total'][name], temperature=tt)
if (name in xsdict[tt]['nu-fission'].keys()):
xsdata.set_nu_fission(xsdict[tt]['nu-fission'][name],
temperature=tt)
xsdata.set_chi(np.array([1., 0.]), temperature=tt)
return xsdata
def create_micro_xs_dict():
"""Returns micro xs library"""
xs_micro = {}
reactions = ['absorption', 'total', 'scatter', 'nu-fission']
# chi is unnecessary when energy bound is in thermal region
# Temperature 300K
# absorption
xs_micro[300] = {r: {} for r in reactions}
xs_micro[300]['absorption']['H'] = np.array([1.0285E-4, 0.0057])
xs_micro[300]['absorption']['O'] = np.array([7.1654E-5, 3.0283E-6])
xs_micro[300]['absorption']['Zr'] = np.array([4.5918E-5, 3.6303E-5])
xs_micro[300]['absorption']['U235'] = np.array([0.0035, 0.1040])
xs_micro[300]['absorption']['U238'] = np.array([0.0056, 0.0094])
# nu-scatter matrix
xs_micro[300]['scatter']['H'] = np.array([[[0.0910, 0.01469],
[0.0, 0.3316]]])
xs_micro[300]['scatter']['O'] = np.array([[[0.0814, 3.3235E-4],
[0.0, 0.0960]]])
xs_micro[300]['scatter']['Zr'] = np.array([[[0.0311, 2.6373E-5],
[0.0, 0.0315]]])
xs_micro[300]['scatter']['U235'] = np.array([[[0.0311, 2.6373E-5],
[0.0, 0.0315]]])
xs_micro[300]['scatter']['U238'] = np.array([[[0.0551, 2.2341E-5],
[0.0, 0.0526]]])
# nu-fission
xs_micro[300]['nu-fission']['U235'] = np.array([0.0059, 0.2160])
xs_micro[300]['nu-fission']['U238'] = np.array([0.0019, 1.4627E-7])
# total
xs_micro[300]['total']['H'] = xs_micro[300]['absorption']['H'] + \
np.sum(xs_micro[300]['scatter']['H'][0], 1)
xs_micro[300]['total']['O'] = xs_micro[300]['absorption']['O'] + \
np.sum(xs_micro[300]['scatter']['O'][0], 1)
xs_micro[300]['total']['Zr'] = xs_micro[300]['absorption']['Zr'] + \
np.sum(xs_micro[300]['scatter']['Zr'][0], 1)
xs_micro[300]['total']['U235'] = xs_micro[300]['absorption']['U235'] + \
np.sum(xs_micro[300]['scatter']['U235'][0], 1)
xs_micro[300]['total']['U238'] = xs_micro[300]['absorption']['U238'] + \
np.sum(xs_micro[300]['scatter']['U238'][0], 1)
# Temperature 600K
xs_micro[600] = {r: {} for r in reactions}
# absorption
xs_micro[600]['absorption']['H'] = np.array([1.0356E-4, 0.0046])
xs_micro[600]['absorption']['O'] = np.array([7.2678E-5, 2.4963E-6])
xs_micro[600]['absorption']['Zr'] = np.array([4.7256E-5, 2.9757E-5])
xs_micro[600]['absorption']['U235'] = np.array([0.0035, 0.0853])
xs_micro[600]['absorption']['U238'] = np.array([0.0058, 0.0079])
# nu-scatter matrix
xs_micro[600]['scatter']['H'] = np.array([[[0.0910, 0.0138],
[0.0, 0.3316]]])
xs_micro[600]['scatter']['O'] = np.array([[[0.0814, 3.5367E-4],
[0.0, 0.0959]]])
xs_micro[600]['scatter']['Zr'] = np.array([[[0.0311, 3.2293E-5],
[0.0, 0.0314]]])
xs_micro[600]['scatter']['U235'] = np.array([[[0.0022, 1.9763E-6],
[9.1634E-8, 0.0039]]])
xs_micro[600]['scatter']['U238'] = np.array([[[0.0556, 2.8803E-5],
[0.0, 0.0536]]])
# nu-fission
xs_micro[600]['nu-fission']['U235'] = np.array([0.0059, 0.1767])
xs_micro[600]['nu-fission']['U238'] = np.array([0.0019, 1.2405E-7])
# total
xs_micro[600]['total']['H'] = xs_micro[600]['absorption']['H'] + \
np.sum(xs_micro[600]['scatter']['H'][0], 1)
xs_micro[600]['total']['O'] = xs_micro[600]['absorption']['O'] + \
np.sum(xs_micro[600]['scatter']['O'][0], 1)
xs_micro[600]['total']['Zr'] = xs_micro[600]['absorption']['Zr'] + \
np.sum(xs_micro[600]['scatter']['Zr'][0], 1)
xs_micro[600]['total']['U235'] = xs_micro[600]['absorption']['U235'] + \
np.sum(xs_micro[600]['scatter']['U235'][0], 1)
xs_micro[600]['total']['U238'] = xs_micro[600]['absorption']['U238'] + \
np.sum(xs_micro[600]['scatter']['U238'][0], 1)
# Temperature 900K
xs_micro[900] = {r: {} for r in reactions}
# absorption
xs_micro[900]['absorption']['H'] = np.array([1.0529E-4, 0.0040])
xs_micro[900]['absorption']['O'] = np.array([7.3055E-5, 2.1850E-6])
xs_micro[900]['absorption']['Zr'] = np.array([4.7141E-5, 2.5941E-5])
xs_micro[900]['absorption']['U235'] = np.array([0.0035, 0.0749])
xs_micro[900]['absorption']['U238'] = np.array([0.0060, 0.0071])
# total
xs_micro[900]['total']['H'] = np.array([0.2982, 0.7332])
xs_micro[900]['total']['O'] = np.array([0.0885, 0.1004])
xs_micro[900]['total']['Zr'] = np.array([0.0370, 0.0317])
xs_micro[900]['total']['U235'] = np.array([0.0061, 0.0789])
xs_micro[900]['total']['U238'] = np.array([0.0707, 0.0613])
# nu-scatter matrix
xs_micro[900]['scatter']['H'] = np.array([[[0.0913, 0.0147],
[0.0, 0.4020]]])
xs_micro[900]['scatter']['O'] = np.array([[[0.0812, 4.0413E-4],
[0.0, 0.0965]]])
xs_micro[900]['scatter']['Zr'] = np.array([[[0.0311, 3.6735E-5],
[0.0, 0.0314]]])
xs_micro[900]['scatter']['U235'] = np.array([[[0.0022, 2.9034E-6],
[1.3117E-8, 0.0039]]])
xs_micro[900]['scatter']['U238'] = np.array([[[0.0560, 3.7619E-5],
[0.0, 0.0538]]])
# nu-fission
xs_micro[900]['nu-fission']['U235'] = np.array([0.0059, 0.1545])
xs_micro[900]['nu-fission']['U238'] = np.array([0.0019, 1.1017E-7])
# total
xs_micro[900]['total']['H'] = xs_micro[900]['absorption']['H'] + \
np.sum(xs_micro[900]['scatter']['H'][0], 1)
xs_micro[900]['total']['O'] = xs_micro[900]['absorption']['O'] + \
np.sum(xs_micro[900]['scatter']['O'][0], 1)
xs_micro[900]['total']['Zr'] = xs_micro[900]['absorption']['Zr'] + \
np.sum(xs_micro[900]['scatter']['Zr'][0], 1)
xs_micro[900]['total']['U235'] = xs_micro[900]['absorption']['U235'] + \
np.sum(xs_micro[900]['scatter']['U235'][0], 1)
xs_micro[900]['total']['U238'] = xs_micro[900]['absorption']['U238'] + \
np.sum(xs_micro[900]['scatter']['U238'][0], 1)
# roll axis for scatter matrix
for t in xs_micro:
for n in xs_micro[t]['scatter']:
xs_micro[t]['scatter'][n] = np.rollaxis(xs_micro[t]['scatter'][n],
0, 3)
return xs_micro
def create_macro_dict(xs_micro):
"""Create a dictionary with two group cross-section"""
xs_macro = {}
for t, d1 in xs_micro.items():
xs_macro[t] = {}
for r, d2 in d1.items():
temp = []
xs_macro[t][r] = {}
for n, v in d2.items():
temp.append(d2[n])
# The name 'macro' is needed to store data at the same level
# of a xs_macro dictionary as for xs_micro and use it in
# function build_openmc_xs_lib
xs_macro[t][r]['macro'] = sum(temp)
return xs_macro
def create_openmc_2mg_libs(names):
"""Built a micro/macro two group openmc MGXS libraries"""
# Initialized library params
group_edges = [0.0, 0.625, 20.0e6]
groups = openmc.mgxs.EnergyGroups(group_edges=group_edges)
mg_cross_sections_file_micro = openmc.MGXSLibrary(groups)
mg_cross_sections_file_macro = openmc.MGXSLibrary(groups)
# Building a micro mg library
micro_cs = create_micro_xs_dict()
for name in names:
mg_cross_sections_file_micro.add_xsdata(build_openmc_xs_lib(name,
groups,
[t for t in
micro_cs],
micro_cs))
# Building a macro mg library
macro_xs = create_macro_dict(micro_cs)
mg_cross_sections_file_macro.add_xsdata(build_openmc_xs_lib('macro',
groups,
[t for t in
macro_xs],
macro_xs))
# Exporting library to hdf5 files
mg_cross_sections_file_micro.export_to_hdf5('micro_2g.h5')
mg_cross_sections_file_macro.export_to_hdf5('macro_2g.h5')
# Returning the macro_xs dict is needed for analytical solution
return macro_xs
def analytical_solution_2g_therm(xsmin, xsmax=None, wgt=1.0):
""" Calculate eigenvalue based on analytical solution for eq Lf = (1/k)Qf
in two group for infinity dilution media in assumption of group
boundary in thermal spectra < 1.e+3 Ev
Parameters:
----------
xsmin : dict
macro cross-sections dictionary with minimum range temperature
xsmax : dict
macro cross-sections dictionary with maximum range temperature
by default: None not used for standalone temperature
wgt : float
weight for interpolation by default 1.0
Returns:
-------
keff : np.float64
analytical eigenvalue of critical eq matrix
"""
if xsmax is None:
sa = xsmin['absorption']['macro']
ss12 = xsmin['scatter']['macro'][0][1][0]
nsf = xsmin['nu-fission']['macro']
else:
sa = xsmin['absorption']['macro'] * wgt + \
xsmax['absorption']['macro'] * (1 - wgt)
ss12 = xsmin['scatter']['macro'][0][1][0] * wgt + \
xsmax['scatter']['macro'][0][1][0] * (1 - wgt)
nsf = xsmin['nu-fission']['macro'] * wgt + \
xsmax['nu-fission']['macro'] * (1 - wgt)
L = np.array([sa[0] + ss12, 0.0, -ss12, sa[1]]).reshape(2, 2)
Q = np.array([nsf[0], nsf[1], 0.0, 0.0]).reshape(2, 2)
arr = np.linalg.inv(L).dot(Q)
return np.amax(np.linalg.eigvals(arr))
def build_inf_model(xsnames, xslibname, temperature, tempmethod='nearest'):
""" Building an infinite medium for openmc multi-group testing
Parameters:
----------
xsnames : list of str()
list with xs names
xslibname:
name of hdf5 file with cross-section library
temperature : float
value of a current temperature in K
tempmethod : {'nearest', 'interpolation'}
by default 'nearest'
"""
model = openmc.Model()
inf_medium = openmc.Material(name='test material', material_id=1)
inf_medium.set_density("sum")
for xs in xsnames:
inf_medium.add_nuclide(xs, 1)
INF = 11.1
# Instantiate a Materials collection and export to XML
materials_file = openmc.Materials([inf_medium])
materials_file.cross_sections = xslibname
model.materials = materials_file
# Instantiate boundary Planes
min_x = openmc.XPlane(boundary_type='reflective', x0=-INF)
max_x = openmc.XPlane(boundary_type='reflective', x0=INF)
min_y = openmc.YPlane(boundary_type='reflective', y0=-INF)
max_y = openmc.YPlane(boundary_type='reflective', y0=INF)
# Instantiate a Cell
cell = openmc.Cell(cell_id=1, name='cell')
cell.temperature = temperature
# Register bounding Surfaces with the Cell
cell.region = +min_x & -max_x & +min_y & -max_y
# Fill the Cell with the Material
cell.fill = inf_medium
# Create root universe
root_universe = openmc.Universe(name='root universe', cells=[cell])
# Create Geometry and set root Universe
model.geometry = openmc.Geometry(root_universe)
# OpenMC simulation parameters
batches = 200
inactive = 5
particles = 5000
# Instantiate a Settings object
settings_file = openmc.Settings()
settings_file.batches = batches
settings_file.inactive = inactive
settings_file.particles = particles
settings_file.energy_mode = 'multi-group'
settings_file.output = {'summary': False}
# Create an initial uniform spatial source distribution over fissionable zones
bounds = [-INF, -INF, -INF, INF, INF, INF]
uniform_dist = openmc.stats.Box(bounds[:3], bounds[3:], only_fissionable=True)
settings_file.temperature = {'method': tempmethod}
settings_file.source = openmc.Source(space=uniform_dist)
model.settings = settings_file
model.export_to_model_xml()

View file

@ -1,13 +0,0 @@
<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0 0 2" />
<surface id="2" type="z-cylinder" coeffs="0 0 5" />
<surface id="3" type="z-cylinder" coeffs="0 0 10" boundary="vacuum" />
<surface id="4" type="y-plane" coeffs="5" boundary="vacuum" />
<cell id="1" material="1" region=" -1 -4" />
<cell id="2" material="3" region="1 -2 -4" />
<cell id="3" material="2" region="2 -3 -4" />
</geometry>

View file

@ -1,19 +0,0 @@
<?xml version="1.0"?>
<materials>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="2">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="3">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

View file

@ -0,0 +1,76 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="3">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 -4" universe="0" />
<cell id="2" material="3" region="1 -2 -4" universe="0" />
<cell id="3" material="2" region="2 -3 -4" universe="0" />
<surface coeffs="0.0 0.0 2.0" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 5.0" id="2" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 10.0" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="5.0" id="4" type="y-plane" />
</geometry>
<settings>
<run_mode>plot</run_mode>
<entropy_mesh>1</entropy_mesh>
<mesh id="1">
<dimension>5 4 3</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
</settings>
<tallies>
<mesh id="2" type="rectilinear">
<x_grid>-10.0 10.0</x_grid>
<y_grid>-10.0 10.0</y_grid>
<z_grid>-10.0 0.0 5.0 7.5 8.75 10.0</z_grid>
</mesh>
<filter id="1" type="mesh">
<bins>2</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>
<plots>
<plot basis="xy" color_by="cell" id="1" type="slice">
<origin>0.0 0.0 0.0</origin>
<width>25.0 25.0</width>
<pixels>200 200</pixels>
<color id="1" rgb="255 0 0" />
<meshlines linewidth="0" meshtype="entropy" />
</plot>
<plot basis="xz" color_by="cell" id="2" type="slice">
<origin>0.0 0.0 0.0</origin>
<width>25.0 25.0</width>
<pixels>200 200</pixels>
<mask background="255 255 255" components="1 3" />
<meshlines id="2" linewidth="0" meshtype="tally" />
</plot>
<plot basis="yz" color_by="material" id="3" type="slice">
<origin>0.0 0.0 0.0</origin>
<width>25.0 25.0</width>
<pixels>200 200</pixels>
<background>0 0 0</background>
</plot>
<plot color_by="cell" id="4" type="voxel">
<origin>0.0 0.0 0.0</origin>
<width>20.0 20.0 10.0</width>
<pixels>100 100 10</pixels>
</plot>
</plots>
</model>

View file

@ -1,33 +0,0 @@
<?xml version="1.0"?>
<plots>
<plot id="1" basis="xy">
<origin>0. 0. 0.</origin>
<width>25 25</width>
<pixels>200 200</pixels>
<color id="1" rgb="255 0 0" /> <!-- Red -->
<meshlines meshtype="entropy" linewidth="0" />
</plot>
<plot id="2" basis="xz">
<origin>0. 0. 0.</origin>
<width>25 25</width>
<pixels>200 200</pixels>
<mask components="1 3" background="255 255 255" />
<meshlines meshtype="tally" id="2" linewidth="0" />
</plot>
<plot id="3" basis="yz" color_by="material">
<origin>0. 0. 0.</origin>
<width>25 25</width>
<pixels>200 200</pixels>
<background>0 0 0</background>
</plot>
<plot id="4" type="voxel">
<pixels>100 100 10</pixels>
<origin>0. 0. 0.</origin>
<width>20 20 10</width>
</plot>
</plots>

View file

@ -1,13 +0,0 @@
<?xml version="1.0"?>
<settings>
<run_mode>plot</run_mode>
<mesh id="1">
<dimension>5 4 3</dimension>
<lower_left>-10 -10 -10</lower_left>
<upper_right>10 10 10</upper_right>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

View file

@ -1,20 +0,0 @@
<?xml version="1.0"?>
<tallies>
<mesh id="2" type="rectilinear">
<x_grid>-10 10</x_grid>
<y_grid>-10 10</y_grid>
<z_grid>-10 0 5 7.5 8.75 10</z_grid>
</mesh>
<filter id="1">
<type>mesh</type>
<bins>2</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>

View file

@ -1,14 +0,0 @@
<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0 0 2" />
<surface id="20" type="z-cylinder" coeffs="0 0 5.5" />
<surface id="2" type="z-cylinder" coeffs="0 0 5" />
<surface id="3" type="z-cylinder" coeffs="0 0 10" boundary="vacuum" />
<surface id="4" type="y-plane" coeffs="5" boundary="vacuum" />
<cell id="1" material="1" region=" -1 -4" />
<cell id="2" material="3" region="1 -20 -4" />
<cell id="3" material="2" region="2 -3 -4" />
</geometry>

View file

@ -1,19 +0,0 @@
<?xml version="1.0"?>
<materials>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="2">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="3">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

View file

@ -0,0 +1,65 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="3">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 -4" universe="0" />
<cell id="2" material="3" region="1 -20 -4" universe="0" />
<cell id="3" material="2" region="2 -3 -4" universe="0" />
<surface coeffs="0.0 0.0 2.0" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 5.0" id="2" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 10.0" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="5.0" id="4" type="y-plane" />
<surface coeffs="0.0 0.0 5.5" id="20" type="z-cylinder" />
</geometry>
<settings>
<run_mode>plot</run_mode>
<entropy_mesh>1</entropy_mesh>
<mesh id="1">
<dimension>5 4 3</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
</settings>
<plots>
<plot basis="xy" color_by="cell" id="1" type="slice">
<origin>0.0 0.0 0.0</origin>
<width>25.0 25.0</width>
<pixels>200 200</pixels>
<color id="1" rgb="255 0 0" />
<show_overlaps>true</show_overlaps>
<meshlines id="1" linewidth="0" meshtype="entropy" />
</plot>
<plot basis="xz" color_by="cell" id="2" type="slice">
<origin>0.0 0.0 0.0</origin>
<width>25.0 25.0</width>
<pixels>200 200</pixels>
<mask background="255 255 255" components="1 3" />
<show_overlaps>true</show_overlaps>
<overlap_color>255 211 0</overlap_color>
</plot>
<plot basis="yz" color_by="material" id="3" type="slice">
<origin>0.0 0.0 0.0</origin>
<width>25.0 25.0</width>
<pixels>200 200</pixels>
<background>0 0 0</background>
</plot>
<plot color_by="cell" id="4" type="voxel">
<origin>0.0 0.0 0.0</origin>
<width>20.0 20.0 10.0</width>
<pixels>100 100 10</pixels>
</plot>
</plots>
</model>

View file

@ -1,35 +0,0 @@
<?xml version="1.0"?>
<plots>
<plot id="1" basis="xy">
<origin>0. 0. 0.</origin>
<width>25 25</width>
<pixels>200 200</pixels>
<color id="1" rgb="255 0 0" /> <!-- Red -->
<meshlines meshtype="entropy" linewidth="0" />
<show_overlaps>true</show_overlaps>
</plot>
<plot id="2" basis="xz">
<origin>0. 0. 0.</origin>
<width>25 25</width>
<pixels>200 200</pixels>
<mask components="1 3" background="255 255 255" />
<show_overlaps>true</show_overlaps>
<overlap_color>255 211 0</overlap_color>
</plot>
<plot id="3" basis="yz" color_by="material">
<origin>0. 0. 0.</origin>
<width>25 25</width>
<pixels>200 200</pixels>
<background>0 0 0</background>
</plot>
<plot id="4" type="voxel">
<pixels>100 100 10</pixels>
<origin>0. 0. 0.</origin>
<width>20 20 10</width>
</plot>
</plots>

View file

@ -1,13 +0,0 @@
<?xml version="1.0"?>
<settings>
<run_mode>plot</run_mode>
<mesh id="1">
<dimension>5 4 3</dimension>
<lower_left>-10 -10 -10</lower_left>
<upper_right>10 10 10</upper_right>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

View file

@ -1,13 +0,0 @@
<?xml version="1.0"?>
<geometry>
<surface id="1" type="z-cylinder" coeffs="0 0 2" />
<surface id="2" type="z-cylinder" coeffs="0 0 5" />
<surface id="3" type="z-cylinder" coeffs="0 0 10" boundary="vacuum" />
<surface id="4" type="y-plane" coeffs="5" boundary="vacuum" />
<cell id="1" material="1" region=" -1 -4" />
<cell id="2" material="3" region="1 -2 -4" />
<cell id="3" material="2" region="2 -3 -4" />
</geometry>

View file

@ -1,19 +0,0 @@
<?xml version="1.0"?>
<materials>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="2">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="3">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

View file

@ -0,0 +1,42 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material depletable="true" id="1">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="2">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
<material depletable="true" id="3">
<density units="g/cc" value="4.5" />
<nuclide ao="1.0" name="U235" />
</material>
</materials>
<geometry>
<cell id="1" material="1" region="-1 -4" universe="0" />
<cell id="2" material="3" region="1 -2 -4" universe="0" />
<cell id="3" material="2" region="2 -3 -4" universe="0" />
<surface coeffs="0.0 0.0 2.0" id="1" type="z-cylinder" />
<surface coeffs="0.0 0.0 5.0" id="2" type="z-cylinder" />
<surface boundary="vacuum" coeffs="0.0 0.0 10.0" id="3" type="z-cylinder" />
<surface boundary="vacuum" coeffs="5.0" id="4" type="y-plane" />
</geometry>
<settings>
<run_mode>plot</run_mode>
<entropy_mesh>1</entropy_mesh>
<mesh id="1">
<dimension>5 4 3</dimension>
<lower_left>-10.0 -10.0 -10.0</lower_left>
<upper_right>10.0 10.0 10.0</upper_right>
</mesh>
</settings>
<plots>
<plot color_by="cell" id="4" type="voxel">
<origin>0.0 0.0 0.0</origin>
<width>20.0 20.0 10.0</width>
<pixels>50 50 10</pixels>
</plot>
</plots>
</model>

View file

@ -1,10 +0,0 @@
<?xml version="1.0"?>
<plots>
<plot id="4" type="voxel">
<pixels>50 50 10</pixels>
<origin>0. 0. 0.</origin>
<width>20 20 10</width>
</plot>
</plots>

View file

@ -1,13 +0,0 @@
<?xml version="1.0"?>
<settings>
<run_mode>plot</run_mode>
<mesh id="1">
<dimension>5 4 3</dimension>
<lower_left>-10 -10 -10</lower_left>
<upper_right>10 10 10</upper_right>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

View file

@ -1,305 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<geometry>
<!-- Based on ISCBEP model for leu-comp-therm-008 benchmarks (see LA-UR-10-06230) -->
<!-- pin-cell surfaces -->
<surface id="1" type="z-cylinder" coeffs="0.0 0.0 0.514858"/> <!-- fuel OR -->
<surface id="2" type="z-cylinder" coeffs="0.0 0.0 0.602996"/> <!-- fuel clad OR -->
<surface id="3" type="z-cylinder" coeffs="0.0 0.0 0.585000"/> <!-- pyrex OR -->
<surface id="99" type="sphere" coeffs="0.0 0.0 0.0 400.0"/> <!-- dummy outer boundary -->
<!-- pin-cell construction -->
<!-- Water pin-cell -->
<cell id="11" universe="1" material="1" region="-99"/>
<cell id="12" universe="1" material="1" region=" 99"/>
<!-- Fuel Rod -->
<cell id="21" universe="2" material="2" region=" -1"/> <!-- fuel -->
<cell id="22" universe="2" material="3" region="1 -2"/> <!-- clad -->
<cell id="23" universe="2" material="1" region=" 2"/> <!-- water -->
<!-- Pyrex Rod -->
<cell id="31" universe="3" material="4" region=" -3"/> <!-- pyrex -->
<cell id="32" universe="3" material="1" region=" 3"/> <!-- water -->
<!-- Assembly construction -->
<!-- Dummy Water Assembly Universe -->
<cell id="99" universe="999" fill="1" region="-99"/>
<!-- Central Fuel Assemblies -->
<!-- Central Fuel Assembly -->
<lattice id="11" dimension="15 15">
<lower_left> -12.2682 -12.2682 </lower_left>
<pitch> 1.63576 1.63576 </pitch>
<universes>
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 1 2 2 2 1 2 2 2 2 2
2 2 2 3 2 2 2 2 2 2 2 3 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 1 2 2 1 2 2 2 1 2 2 1 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 1 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 1 2 2 1 2 2 2 1 2 2 1 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 3 2 2 2 2 2 2 2 3 2 2 2
2 2 2 2 2 1 2 2 2 1 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
</universes>
</lattice>
<cell id="111" universe="111" fill="11" region=""/>
<!-- North Fuel Assembly -->
<lattice id="22" dimension="15 15">
<lower_left> -12.2682 -12.2682 </lower_left>
<pitch> 1.63576 1.63576 </pitch>
<universes>
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 1 2 2 2 1 2 2 2 2 2
2 2 2 1 2 2 2 2 2 2 2 1 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 1 2 2 1 2 2 2 1 2 2 1 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 1 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 1 2 2 1 2 2 2 1 2 2 1 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 3 2 2 2 2 2 2 2 3 2 2 2
2 2 2 2 2 1 2 2 2 1 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
</universes>
</lattice>
<cell id="222" universe="222" fill="22" region=""/> <!-- north -->
<cell id="444" universe="444" fill="222" region="" rotation="0 0 90"/> <!-- west -->
<cell id="555" universe="555" fill="222" region="" rotation="0 0 180"/> <!-- south -->
<cell id="666" universe="666" fill="222" region="" rotation="0 0 270"/> <!-- east -->
<!-- Northeast Fuel Assembly -->
<lattice id="33" dimension="15 15">
<lower_left> -12.2682 -12.2682 </lower_left>
<pitch> 1.63576 1.63576 </pitch>
<universes>
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 1 2 2 2 1 2 2 2 2 2
2 2 2 1 2 2 2 2 2 2 2 1 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 1 2 2 1 2 2 2 1 2 2 1 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 1 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 1 2 2 1 2 2 2 1 2 2 1 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 3 2 2 2 2 2 2 2 1 2 2 2
2 2 2 2 2 1 2 2 2 1 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
</universes>
</lattice>
<cell id="333" universe="333" fill="33" region=""/> <!-- northeast -->
<cell id="777" universe="777" fill="333" region="" rotation="0 0 90"/> <!-- northwest -->
<cell id="888" universe="888" fill="333" region="" rotation="0 0 180"/> <!-- southwest -->
<cell id="998" universe="998" fill="333" region="" rotation="0 0 270"/> <!-- southeast -->
<!-- Surrounding Driver Assemblies -->
<!-- Full Driver Assembly -->
<lattice id="24" dimension="15 15">
<lower_left> -12.2682 -12.2682 </lower_left>
<pitch> 1.63576 1.63576 </pitch>
<universes>
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
</universes>
</lattice>
<cell id="240" universe="240" fill="24" region="-99"/>
<!-- North Edge -->
<lattice id="14" dimension="15 15">
<lower_left> -12.2682 -12.2682 </lower_left>
<pitch> 1.63576 1.63576 </pitch>
<universes>
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 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 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 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 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 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
</universes>
</lattice>
<cell id="140" universe="140" fill="14" region=""/> <!-- north -->
<cell id="410" universe="410" fill="140" region="" rotation="0 0 90"/> <!-- east -->
<cell id="740" universe="740" fill="140" region="" rotation="0 0 180"/> <!-- south -->
<cell id="470" universe="470" fill="140" region="" rotation="0 0 270"/> <!-- west -->
<!-- Northeast Edge Corner -->
<lattice id="15" dimension="15 15">
<lower_left> -12.2682 -12.2682 </lower_left>
<pitch> 1.63576 1.63576 </pitch>
<universes>
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 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 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 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 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 2 2 1 1 1 1 1 1 1 1 1 1 1 1
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1
</universes>
</lattice>
<cell id="150" universe="150" fill="15" region=""/> <!-- northeast -->
<cell id="130" universe="130" fill="150" region="" rotation="0 0 90"/> <!-- northwest -->
<cell id="510" universe="510" fill="150" region="" rotation="0 0 180"/> <!-- southwest -->
<cell id="570" universe="570" fill="150" region="" rotation="0 0 270"/> <!-- southeast -->
<!-- Northeast Top Steps -->
<lattice id="25" dimension="15 15">
<lower_left> -12.2682 -12.2682 </lower_left>
<pitch> 1.63576 1.63576 </pitch>
<universes>
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
</universes>
</lattice>
<cell id="250" universe="250" fill="25" region=""/> <!-- northeast -->
<cell id="320" universe="320" fill="250" region="" rotation="0 0 90"/> <!-- northwest -->
<cell id="630" universe="630" fill="250" region="" rotation="0 0 180"/> <!-- southwest -->
<cell id="560" universe="560" fill="250" region="" rotation="0 0 270"/> <!-- southeast -->
<!-- Northeast Middle Corner -->
<lattice id="26" dimension="15 15">
<lower_left> -12.2682 -12.2682 </lower_left>
<pitch> 1.63576 1.63576 </pitch>
<universes>
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 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 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 2 2 2 2 2 2 2 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
</universes>
</lattice>
<cell id="260" universe="260" fill="26" region=""/> <!-- northeast -->
<cell id="220" universe="220" fill="260" region="" rotation="0 0 90"/> <!-- southeast -->
<cell id="620" universe="620" fill="260" region="" rotation="0 0 180"/> <!-- southwest -->
<cell id="660" universe="660" fill="260" region="" rotation="0 0 270"/> <!-- northwest -->
<!-- Northeast Bottom Steps -->
<lattice id="36" dimension="15 15">
<lower_left> -12.2682 -12.2682 </lower_left>
<pitch> 1.63576 1.63576 </pitch>
<universes>
2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
</universes>
</lattice>
<cell id="360" universe="360" fill="36" region=""/> <!-- northeast -->
<cell id="230" universe="230" fill="360" region="" rotation="0 0 90"/> <!-- southeast -->
<cell id="520" universe="520" fill="360" region="" rotation="0 0 180"/> <!-- southwest -->
<cell id="650" universe="650" fill="360" region="" rotation="0 0 270"/> <!-- northwest -->
<!-- Core construction -->
<!-- Core Surfaces -->
<surface id="10" type="z-plane" coeffs=" -81.662" boundary="vacuum"/>
<surface id="20" type="z-plane" coeffs=" 81.662" boundary="vacuum"/>
<surface id="30" type="z-cylinder" coeffs="0.0 0.0 76.200" />
<surface id="40" type="z-cylinder" coeffs="0.0 0.0 77.470" boundary="vacuum"/>
<!-- Core lattice -->
<lattice id="99" dimension="7 7">
<lower_left> -85.8774 -85.8774 </lower_left>
<pitch> 24.5364 24.5364 </pitch>
<universes>
999 999 130 140 150 999 999
999 220 230 240 250 260 999
130 320 777 222 333 360 150
410 240 444 111 666 240 470
510 520 888 555 998 560 570
999 620 630 240 650 660 999
999 999 510 740 570 999 999
</universes>
</lattice>
<!-- Core Bounding Cell -->
<cell id="1111" universe="0" fill="99" region="10 -20 -30"/>
<cell id="1112" universe="0" material="3" region="10 -20 30 -40"/>
</geometry>

View file

@ -1,95 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- material 1: Water with 1511 PPM -->
<material id="1">
<density value="0.99823" units="g/cc" />
<nuclide name="H1" ao="6.6737E-002" />
<nuclide name="O16" ao="3.3369E-002" />
<nuclide name="B10" ao="1.6769E-005" />
<nuclide name="B11" ao="6.7497E-005" />
<sab name="c_H_in_H2O" />
</material>
<!-- material 2: Fuel (2.459 w/o with B-10 for impurities) -->
<material id="2">
<density value="10.24" units="g/cc" />
<nuclide name="U235" ao="5.6868E-004" />
<!-- <nuclide name="U234" ao="4.5689E-006" /> -->
<nuclide name="U238" ao="2.2268E-002" />
<nuclide name="O16" ao="4.5683E-002" />
<nuclide name="B10" ao="2.6055E-007" />
</material>
<!-- Zircaloy-4 -->
<material id="3">
<density value=" 6.55" units="g/cc" />
<nuclide name="O16" ao="3.0743e-04" />
<!-- <nuclide name="O17" ao="7.4887e-07" />-->
<!-- <nuclide name="Cr50" ao="3.2962e-06" />-->
<!-- <nuclide name="Cr52" ao="6.3564e-05" />-->
<!-- <nuclide name="Cr53" ao="7.2076e-06" />-->
<!-- <nuclide name="Cr54" ao="1.7941e-06" />-->
<!-- <nuclide name="Fe54" ao="8.6699e-06" />-->
<!-- <nuclide name="Fe56" ao="1.3610e-04" />-->
<!-- <nuclide name="Fe57" ao="3.1431e-06" />-->
<!-- <nuclide name="Fe58" ao="4.1829e-07" />-->
<nuclide name="Zr90" ao="2.1827e-02" />
<nuclide name="Zr91" ao="4.7600e-03" />
<nuclide name="Zr92" ao="7.2758e-03" />
<nuclide name="Zr94" ao="7.3734e-03" />
<nuclide name="Zr96" ao="1.1879e-03" />
<!-- <nuclide name="Sn112" ao="4.6735e-06" />-->
<!-- <nuclide name="Sn114" ao="3.1799e-06" />-->
<!-- <nuclide name="Sn115" ao="1.6381e-06" />-->
<!-- <nuclide name="Sn116" ao="7.0055e-05" />-->
<!-- <nuclide name="Sn117" ao="3.7003e-05" />-->
<!-- <nuclide name="Sn118" ao="1.1669e-04" />-->
<!-- <nuclide name="Sn119" ao="4.1387e-05" />-->
<!-- <nuclide name="Sn120" ao="1.5697e-04" />-->
<!-- <nuclide name="Sn122" ao="2.2308e-05" />-->
<!-- <nuclide name="Sn124" ao="2.7897e-05" />-->
</material>
<!-- material 3: Fuel Aluminum 6061 cladding -->
<!-- <material id="3">-->
<!-- <density value="2.5052" units="g/cc" />-->
<!-- <nuclide name="Al27" ao="5.3985e-02" />-->
<!-- <nuclide name="Mn55" ao="4.1191e-05" />-->
<!-- <nuclide name="Mg24" ao="4.9031e-04" />-->
<!-- <nuclide name="Mg25" ao="6.2072e-05" />-->
<!-- <nuclide name="Mg26" ao="6.8341e-05" />-->
<!-- <nuclide name="Si28" ao="2.9726e-04" />-->
<!-- <nuclide name="Si29" ao="1.5094e-05" />-->
<!-- <nuclide name="Si30" ao="9.9499e-06" />-->
<!-- <nuclide name="Cr50" ao="2.5214e-06" />-->
<!-- <nuclide name="Cr52" ao="4.8622e-05" />-->
<!-- <nuclide name="Cr53" ao="5.5133e-06" />-->
<!-- <nuclide name="Cr54" ao="1.3724e-06" />-->
<!-- <nuclide name="Fe54" ao="1.1053e-05" />-->
<!-- <nuclide name="Fe56" ao="1.7351e-04" />-->
<!-- <nuclide name="Fe57" ao="4.0070e-06" />-->
<!-- <nuclide name="Fe58" ao="5.3326e-07" />-->
<!-- <nuclide name="Ti46" ao="3.8992e-06" />-->
<!-- <nuclide name="Ti47" ao="3.5164e-06" />-->
<!-- <nuclide name="Ti48" ao="3.4842e-05" />-->
<!-- <nuclide name="Ti49" ao="2.5569e-06" />-->
<!-- <nuclide name="Ti50" ao="2.4482e-06" />-->
<!-- <nuclide name="Cu63" ao="4.1054e-05" />-->
<!-- <nuclide name="Cu65" ao="1.8299e-05" />-->
<!-- </material>-->
<!-- material 4: Control Rod Material -->
<material id="4">
<density value="2.2442" units="g/cc" />
<nuclide name="B10" ao="9.7491e-4" />
<nuclide name="B11" ao="3.9241e-3" />
<nuclide name="O16" ao="4.4829e-2" />
<!-- <nuclide name="Na23" ao="1.7444e-3" />-->
<!-- <nuclide name="Al27" ao="1.0018e-3" />-->
<!-- <nuclide name="Si28" ao="1.6884e-02" />-->
<!-- <nuclide name="Si29" ao="8.5730e-04" />-->
<!-- <nuclide name="Si30" ao="5.6513e-04" />-->
</material>
</materials>

View file

@ -0,0 +1,299 @@
<?xml version='1.0' encoding='utf-8'?>
<model>
<materials>
<material id="1">
<density units="g/cc" value="0.99823" />
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<nuclide ao="0.033369" name="O16" />
<nuclide ao="1.6769e-05" name="B10" />
<nuclide ao="6.7497e-05" name="B11" />
<sab name="c_H_in_H2O" />
</material>
<material depletable="true" id="2">
<density units="g/cc" value="10.24" />
<nuclide ao="0.00056868" name="U235" />
<nuclide ao="0.022268" name="U238" />
<nuclide ao="0.045683" name="O16" />
<nuclide ao="2.6055e-07" name="B10" />
</material>
<material id="3">
<density units="g/cc" value="6.55" />
<nuclide ao="0.00030743" name="O16" />
<nuclide ao="0.021827" name="Zr90" />
<nuclide ao="0.00476" name="Zr91" />
<nuclide ao="0.0072758" name="Zr92" />
<nuclide ao="0.0073734" name="Zr94" />
<nuclide ao="0.0011879" name="Zr96" />
</material>
<material id="4">
<density units="g/cc" value="2.2442" />
<nuclide ao="0.00097491" name="B10" />
<nuclide ao="0.0039241" name="B11" />
<nuclide ao="0.044829" name="O16" />
</material>
</materials>
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<pitch>1.63576 1.63576</pitch>
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 1 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 1 2 2 1 2 2 2 1 2 2 1 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 3 2 2 2 2 2 2 2 3 2 2 2
2 2 2 2 2 1 2 2 2 1 2 2 2 2 2
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<pitch>1.63576 1.63576</pitch>
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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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 1 1 1 1 1 1
1 1 1 1 1 1 1 1 1 1 1 1 1 1 1
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2 2 2 1 1 1 1 1 1 1 1 1 1 1 1
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1
2 2 2 1 1 1 1 1 1 1 1 1 1 1 1 </universes>
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<pitch>1.63576 1.63576</pitch>
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<lower_left>-12.2682 -12.2682</lower_left>
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 1 2 2 2 1 2 2 2 2 2
2 2 2 1 2 2 2 2 2 2 2 1 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 1 2 2 1 2 2 2 1 2 2 1 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 1 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 1 2 2 1 2 2 2 1 2 2 1 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 3 2 2 2 2 2 2 2 3 2 2 2
2 2 2 2 2 1 2 2 2 1 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 </universes>
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<lattice id="24">
<pitch>1.63576 1.63576</pitch>
<dimension>15 15</dimension>
<lower_left>-12.2682 -12.2682</lower_left>
<universes>
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 </universes>
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<pitch>1.63576 1.63576</pitch>
<dimension>15 15</dimension>
<lower_left>-12.2682 -12.2682</lower_left>
<universes>
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2 2 2 1 1 1 1 1 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
2 2 2 2 2 2 2 2 2 2 2 2 2 1 1
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
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<pitch>1.63576 1.63576</pitch>
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2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
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2 2 2 2 2 2 2 2 2 2 2 2 2 2 2
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2 2 2 2 2 1 2 2 2 1 2 2 2 2 2
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<pitch>1.63576 1.63576</pitch>
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2 2 2 2 2 2 2 2 1 1 1 1 1 1 1
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<settings>
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</space>
</source>
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</settings>
</model>

View file

@ -1,23 +0,0 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<run_mode>eigenvalue</run_mode>
<batches>2</batches>
<inactive>0</inactive>
<particles>100</particles>
<!-- Starting source -->
<source>
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
<track>
1 1 1
1 1 30
2 1 60
</track>
</settings>