Updated lattice example with simple and nested versions.

This commit is contained in:
Paul Romano 2011-12-02 03:44:38 -05:00
parent a843d245b6
commit 76ed79fc21
12 changed files with 188 additions and 81 deletions

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@ -1,58 +0,0 @@
<?xml version="1.0"?>
<geometry>
<cell id="1">
<universe>0</universe>
<fill>111</fill>
<surfaces>1 -2 3 -4</surfaces>
</cell>
<cell id="100">
<universe>3</universe>
<material>40</material>
<surfaces>-5</surfaces>
</cell>
<cell id="101">
<universe>3</universe>
<material>41</material>
<surfaces>5</surfaces>
</cell>
<lattice id="111">
<type>rectangular</type>
<dimension>20 20</dimension>
<origin>-10.0 -10.0</origin>
<width>1.0 1.0</width>
<universes>
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3
</universes>
</lattice>
<surface id="1" type="x-plane" coeffs="-9.9" boundary="vacuum" />
<surface id="2" type="x-plane" coeffs="9.9" boundary="vacuum" />
<surface id="3" type="y-plane" coeffs="-9.9" boundary="vacuum" />
<surface id="4" type="y-plane" coeffs="9.9" boundary="vacuum" />
<surface id="5">
<type>z-cylinder</type>
<coeffs>0.0 0.0 0.4</coeffs>
</surface>
</geometry>

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@ -1,17 +0,0 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="40">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="03c" ao="1.0" />
</material>
<material id="41">
<density value="1.0" units="g/cc" />
<nuclide name="H-1" xs="03c" ao="2.0" />
<nuclide name="O-16" xs="03c" ao="1.0" />
<sab name="lwe7" xs="00t" />
</material>
</materials>

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@ -0,0 +1,45 @@
<?xml version="1.0"?>
<geometry>
<cell id="1" fill="6" surfaces="1 -2 3 -4" />
<cell id="2" universe="5" fill="4" surfaces="1 -2 3 -4" />
<cell id="101" universe="1" material="1" surfaces="-5" />
<cell id="102" universe="1" material="2" surfaces="5" />
<cell id="201" universe="2" material="1" surfaces="-6" />
<cell id="202" universe="2" material="2" surfaces="6" />
<cell id="301" universe="3" material="1" surfaces="-7" />
<cell id="302" universe="3" material="2" surfaces="7" />
<!-- 4 x 4 assembly -->
<lattice id="4">
<type>rectangular</type>
<dimension>2 2</dimension>
<origin>-1.0 -1.0</origin>
<width>1.0 1.0</width>
<universes>
1 2
2 3
</universes>
</lattice>
<!-- 4 x 4 core -->
<lattice id="6">
<type>rectangular</type>
<dimension>2 2</dimension>
<origin>-2.0 -2.0</origin>
<width>2.0 2.0</width>
<universes>
5 5
5 5
</universes>
</lattice>
<surface id="1" type="x-plane" coeffs="-2.0" boundary="vacuum" />
<surface id="2" type="x-plane" coeffs="2.0" boundary="vacuum" />
<surface id="3" type="y-plane" coeffs="-2.0" boundary="vacuum" />
<surface id="4" type="y-plane" coeffs="2.0" boundary="vacuum" />
<surface id="5" type="z-cylinder" coeffs="0.0 0.0 0.4" />
<surface id="6" type="z-cylinder" coeffs="0.0 0.0 0.3" />
<surface id="7" type="z-cylinder" coeffs="0.0 0.0 0.2" />
</geometry>

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<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<!-- Definition of materials -->
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" ao="1.0" />
</material>
<material id="2">
<density value="1.0" units="g/cc" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<sab name="lwtr" xs="10t" />
</material>
</materials>

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<?xml version="1.0"?>
<plot>
<origin>0. 0. 0.</origin>
<width>3.999 3.999</width>
<pixel>0.01</pixel>
</plot>

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@ -1,11 +1,6 @@
<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Path for cross section library -->
<cross_sections>
/home/paulromano/openmc/cross_sections_serpent.xml
</cross_sections>
<!-- Parameters for criticality calculation -->
<criticality>
<cycles>20</cycles>
@ -13,10 +8,12 @@
<particles>10000</particles>
</criticality>
<verbosity>7</verbosity>
<!-- Starting source -->
<source>
<type>box</type>
<coeffs>-4 -4 -4 4 4 4</coeffs>
<coeffs>-1 -1 -1 1 1 1</coeffs>
</source>
</settings>

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<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>rectangular</type>
<dimension>4 4</dimension>
<origin>-2.0 -2.0</origin>
<width>1.0 1.0</width>
</mesh>
<tally id="1">
<filters>
<mesh>1</mesh>
</filters>
<macros>total</macros>
</tally>
</tallies>

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<?xml version="1.0"?>
<geometry>
<cell id="1" fill="5" surfaces="1 -2 3 -4" />
<cell id="101" universe="1" material="1" surfaces="-5" />
<cell id="102" universe="1" material="2" surfaces="5" />
<cell id="201" universe="2" material="1" surfaces="-6" />
<cell id="202" universe="2" material="2" surfaces="6" />
<cell id="301" universe="3" material="1" surfaces="-7" />
<cell id="302" universe="3" material="2" surfaces="7" />
<lattice id="5">
<type>rectangular</type>
<dimension>4 4</dimension>
<origin>-2.0 -2.0</origin>
<width>1.0 1.0</width>
<universes>
1 2 1 2
2 3 2 3
1 2 1 2
2 3 2 3
</universes>
</lattice>
<surface id="1" type="x-plane" coeffs="-2.0" boundary="vacuum" />
<surface id="2" type="x-plane" coeffs="2.0" boundary="vacuum" />
<surface id="3" type="y-plane" coeffs="-2.0" boundary="vacuum" />
<surface id="4" type="y-plane" coeffs="2.0" boundary="vacuum" />
<surface id="5" type="z-cylinder" coeffs="0.0 0.0 0.4" />
<surface id="6" type="z-cylinder" coeffs="0.0 0.0 0.3" />
<surface id="7" type="z-cylinder" coeffs="0.0 0.0 0.2" />
</geometry>

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<?xml version="1.0"?>
<materials>
<default_xs>70c</default_xs>
<!-- Definition of materials -->
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" ao="1.0" />
</material>
<material id="2">
<density value="1.0" units="g/cc" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<sab name="lwtr" xs="10t" />
</material>
</materials>

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<?xml version="1.0"?>
<plot>
<origin>0. 0. 0.</origin>
<width>3.999 3.999</width>
<pixel>0.01</pixel>
</plot>

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<?xml version="1.0" encoding="UTF-8"?>
<settings>
<!-- Parameters for criticality calculation -->
<criticality>
<cycles>20</cycles>
<inactive>10</inactive>
<particles>10000</particles>
</criticality>
<verbosity>7</verbosity>
<!-- Starting source -->
<source>
<type>box</type>
<coeffs>-1 -1 -1 1 1 1</coeffs>
</source>
</settings>

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<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>rectangular</type>
<dimension>4 4</dimension>
<origin>-2.0 -2.0</origin>
<width>1.0 1.0</width>
</mesh>
<tally id="1">
<filters>
<mesh>1</mesh>
</filters>
<macros>total</macros>
</tally>
</tallies>