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Fixed inputs in examples directory.

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This commit is contained in:
Paul Romano 2012-03-14 11:13:54 -04:00
parent 6b638f2d7b
commit a1b056012e
13 changed files with 41 additions and 41 deletions
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11
examples/basic/materials.xml
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@ -1,17 +1,18 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<default_xs>70c</default_xs>
<material id="40">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="03c" ao="1.0" />
<nuclide name="U-235" 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" />
<nuclide name="H-1" ao="2.0" />
<nuclide name="O-16" ao="1.0" />
<sab name="lwtr" xs="10t" />
</material>
</materials>

5
examples/basic/settings.xml
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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>15</cycles>

6
examples/basic/tallies.xml
View file

@ -5,7 +5,7 @@
<filters>
<cell>100</cell>
</filters>
<macros>total scatter nu-scatter absorption fission nu-fission</macros>
<scores>total scatter nu-scatter absorption fission nu-fission</scores>
</tally>
<tally id="2">
@ -13,7 +13,7 @@
<cell>100</cell>
<energy>0 20.0</energy>
</filters>
<macros>total scatter nu-scatter absorption fission nu-fission</macros>
<scores>total scatter nu-scatter absorption fission nu-fission</scores>
</tally>
<tally id="3">
@ -22,7 +22,7 @@
<energy>0 20.0</energy>
<energyout>0 20.0</energyout>
</filters>
<macros>scatter nu-scatter nu-fission</macros>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
</tallies>

4
examples/lattice/nested/geometry.xml
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@ -14,7 +14,7 @@
<lattice id="4">
<type>rectangular</type>
<dimension>2 2</dimension>
<origin>-1.0 -1.0</origin>
<lower_left>-1.0 -1.0</lower_left>
<width>1.0 1.0</width>
<universes>
1 2
@ -26,7 +26,7 @@
<lattice id="6">
<type>rectangular</type>
<dimension>2 2</dimension>
<origin>-2.0 -2.0</origin>
<lower_left>-2.0 -2.0</lower_left>
<width>2.0 2.0</width>
<universes>
5 5

6
examples/lattice/nested/plot.xml
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@ -1,6 +0,0 @@
<?xml version="1.0"?>
<plot>
<origin>0. 0. 0.</origin>
<width>3.999 3.999</width>
<pixel>0.01</pixel>
</plot>

10
examples/lattice/nested/plots.xml Normal file
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@ -0,0 +1,10 @@
<?xml version="1.0"?>
<plots>
<plot id="1" color="mat">
<origin>0. 0. 0.</origin>
<width>4.0 4.0</width>
<pixels>400 400</pixels>
</plot>
</plots>

6
examples/lattice/nested/tallies.xml
View file

@ -4,7 +4,7 @@
<mesh id="1">
<type>rectangular</type>
<dimension>4 4</dimension>
<origin>-2.0 -2.0</origin>
<lower_left>-2.0 -2.0</lower_left>
<width>1.0 1.0</width>
</mesh>
@ -13,7 +13,7 @@
<mesh>1</mesh>
</filters>
<macros>total</macros>
<scores>total</scores>
</tally>
</tallies>
</tallies>

2
examples/lattice/simple/geometry.xml
View file

@ -12,7 +12,7 @@
<lattice id="5">
<type>rectangular</type>
<dimension>4 4</dimension>
<origin>-2.0 -2.0</origin>
<lower_left>-2.0 -2.0</lower_left>
<width>1.0 1.0</width>
<universes>
1 2 1 2

6
examples/lattice/simple/plot.xml
View file

@ -1,6 +0,0 @@
<?xml version="1.0"?>
<plot>
<origin>0. 0. 0.</origin>
<width>3.999 3.999</width>
<pixel>0.01</pixel>
</plot>

10
examples/lattice/simple/plots.xml Normal file
View file

@ -0,0 +1,10 @@
<?xml version="1.0"?>
<plots>
<plot id="1" color="mat">
<origin>0. 0. 0.</origin>
<width>4.0 4.0</width>
<pixels>400 400</pixels>
</plot>
</plots>

6
examples/lattice/simple/tallies.xml
View file

@ -4,7 +4,7 @@
<mesh id="1">
<type>rectangular</type>
<dimension>4 4</dimension>
<origin>-2.0 -2.0</origin>
<lower_left>-2.0 -2.0</lower_left>
<width>1.0 1.0</width>
</mesh>
@ -13,7 +13,7 @@
<mesh>1</mesh>
</filters>
<macros>total</macros>
<scores>total</scores>
</tally>
</tallies>
</tallies>

5
examples/reflective/materials.xml
View file

@ -1,10 +1,11 @@
<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<default_xs>70c</default_xs>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U-235" xs="03c" ao="1.0" />
<nuclide name="U-235" ao="1.0" />
</material>
</materials>

5
examples/reflective/settings.xml
View file

@ -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>500</cycles>