mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-28 06:05:58 -04:00
added examples for other nuclear data libraries, changed all to 300 K
This commit is contained in:
Jon Walsh
parent
e462d4878c
commit
e8e8b9d48f
84 changed files with 1413 additions and 3 deletions
18
examples/basic/jeff/materials.xml
Normal file
18
examples/basic/jeff/materials.xml
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<?xml version="1.0"?>
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<materials>
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<default_xs>31c</default_xs>
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<material id="40">
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<density value="4.5" units="g/cc" />
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<nuclide name="U-235" ao="1.0" />
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</material>
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||||
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<material id="41">
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<density value="1.0" units="g/cc" />
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<nuclide name="H-1" ao="2.0" />
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<nuclide name="O-16" ao="1.0" />
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<sab name="lwtr01" xs="31t" />
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</material>
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</materials>
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||||
15
examples/basic/mcnp/geometry.xml
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15
examples/basic/mcnp/geometry.xml
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@ -0,0 +1,15 @@
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<?xml version="1.0"?>
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<geometry>
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<!-- Definition of Cells -->
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<cell id="1" universe="0" fill="37" surfaces="-2" />
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<cell id="100" universe="37" material="40" surfaces="-1" />
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<cell id="101" universe="37" material="41" surfaces="1" />
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<cell id="2" universe="0" material="41" surfaces = "2 -3" />
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||||
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<!-- Defition of Surfaces -->
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<surface id="1" type="z-cylinder" coeffs="0 0 7" />
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||||
<surface id="2" type="z-cylinder" coeffs="0 0 9" />
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||||
<surface id="3" type="z-cylinder" coeffs="0 0 11" boundary="vacuum" />
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</geometry>
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||||
18
examples/basic/mcnp/settings.xml
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18
examples/basic/mcnp/settings.xml
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@ -0,0 +1,18 @@
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|||
<?xml version="1.0"?>
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||||
<settings>
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||||
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<!-- Parameters for k-eigenvalue calculation -->
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<eigenvalue>
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||||
<batches>15</batches>
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||||
<inactive>5</inactive>
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<particles>10000</particles>
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</eigenvalue>
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<!-- Starting source -->
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<source>
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<space type="box">
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<parameters>-4 -4 -4 4 4 4</parameters>
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</space>
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</source>
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</settings>
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22
examples/basic/mcnp/tallies.xml
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22
examples/basic/mcnp/tallies.xml
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@ -0,0 +1,22 @@
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|||
<?xml version="1.0"?>
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<tallies>
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<tally id="1">
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<filter type="cell" bins="100" />
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<scores>total scatter nu-scatter absorption fission nu-fission</scores>
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</tally>
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<tally id="2">
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<filter type="cell" bins="100" />
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<filter type="energy" bins="0 20.0" />
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<scores>total scatter nu-scatter absorption fission nu-fission</scores>
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</tally>
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<tally id="3">
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<filter type="cell" bins="100" />
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<filter type="energy" bins="0 20.0" />
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<filter type="energyout" bins="0 20.0" />
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<scores>scatter nu-scatter nu-fission</scores>
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</tally>
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</tallies>
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15
examples/basic/nndc/geometry.xml
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15
examples/basic/nndc/geometry.xml
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@ -0,0 +1,15 @@
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<?xml version="1.0"?>
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<geometry>
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<!-- Definition of Cells -->
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<cell id="1" universe="0" fill="37" surfaces="-2" />
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<cell id="100" universe="37" material="40" surfaces="-1" />
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<cell id="101" universe="37" material="41" surfaces="1" />
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<cell id="2" universe="0" material="41" surfaces = "2 -3" />
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<!-- Defition of Surfaces -->
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<surface id="1" type="z-cylinder" coeffs="0 0 7" />
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<surface id="2" type="z-cylinder" coeffs="0 0 9" />
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<surface id="3" type="z-cylinder" coeffs="0 0 11" boundary="vacuum" />
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</geometry>
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18
examples/basic/nndc/materials.xml
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18
examples/basic/nndc/materials.xml
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@ -0,0 +1,18 @@
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<?xml version="1.0"?>
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<materials>
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<default_xs>71c</default_xs>
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<material id="40">
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<density value="4.5" units="g/cc" />
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<nuclide name="U-235" ao="1.0" />
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</material>
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<material id="41">
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<density value="1.0" units="g/cc" />
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<nuclide name="H-1" ao="2.0" />
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<nuclide name="O-16" ao="1.0" />
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<sab name="HH2O" xs="71t" />
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</material>
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</materials>
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18
examples/basic/nndc/settings.xml
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18
examples/basic/nndc/settings.xml
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@ -0,0 +1,18 @@
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<?xml version="1.0"?>
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<settings>
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<!-- Parameters for k-eigenvalue calculation -->
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<eigenvalue>
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<batches>15</batches>
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<inactive>5</inactive>
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<particles>10000</particles>
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</eigenvalue>
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<!-- Starting source -->
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<source>
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<space type="box">
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<parameters>-4 -4 -4 4 4 4</parameters>
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</space>
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</source>
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</settings>
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22
examples/basic/nndc/tallies.xml
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22
examples/basic/nndc/tallies.xml
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@ -0,0 +1,22 @@
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<?xml version="1.0"?>
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<tallies>
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<tally id="1">
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<filter type="cell" bins="100" />
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<scores>total scatter nu-scatter absorption fission nu-fission</scores>
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</tally>
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|
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<tally id="2">
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<filter type="cell" bins="100" />
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<filter type="energy" bins="0 20.0" />
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<scores>total scatter nu-scatter absorption fission nu-fission</scores>
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</tally>
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<tally id="3">
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<filter type="cell" bins="100" />
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<filter type="energy" bins="0 20.0" />
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<filter type="energyout" bins="0 20.0" />
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<scores>scatter nu-scatter nu-fission</scores>
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</tally>
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</tallies>
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15
examples/basic/serpent/geometry.xml
Normal file
15
examples/basic/serpent/geometry.xml
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@ -0,0 +1,15 @@
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<?xml version="1.0"?>
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<geometry>
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|
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<!-- Definition of Cells -->
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<cell id="1" universe="0" fill="37" surfaces="-2" />
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<cell id="100" universe="37" material="40" surfaces="-1" />
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<cell id="101" universe="37" material="41" surfaces="1" />
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<cell id="2" universe="0" material="41" surfaces = "2 -3" />
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|
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<!-- Defition of Surfaces -->
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<surface id="1" type="z-cylinder" coeffs="0 0 7" />
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<surface id="2" type="z-cylinder" coeffs="0 0 9" />
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<surface id="3" type="z-cylinder" coeffs="0 0 11" boundary="vacuum" />
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</geometry>
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18
examples/basic/serpent/materials.xml
Normal file
18
examples/basic/serpent/materials.xml
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@ -0,0 +1,18 @@
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<?xml version="1.0"?>
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<materials>
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<default_xs>03c</default_xs>
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<material id="40">
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<density value="4.5" units="g/cc" />
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<nuclide name="U-235" ao="1.0" />
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</material>
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|
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<material id="41">
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<density value="1.0" units="g/cc" />
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<nuclide name="H-1" ao="2.0" />
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<nuclide name="O-16" ao="1.0" />
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<sab name="lwe7" xs="00t" />
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</material>
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</materials>
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18
examples/basic/serpent/settings.xml
Normal file
18
examples/basic/serpent/settings.xml
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@ -0,0 +1,18 @@
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|||
<?xml version="1.0"?>
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<settings>
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<!-- Parameters for k-eigenvalue calculation -->
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<eigenvalue>
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<batches>15</batches>
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<inactive>5</inactive>
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<particles>10000</particles>
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</eigenvalue>
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<!-- Starting source -->
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<source>
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<space type="box">
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<parameters>-4 -4 -4 4 4 4</parameters>
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</space>
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</source>
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</settings>
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22
examples/basic/serpent/tallies.xml
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22
examples/basic/serpent/tallies.xml
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@ -0,0 +1,22 @@
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<?xml version="1.0"?>
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<tallies>
|
||||
|
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<tally id="1">
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<filter type="cell" bins="100" />
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<scores>total scatter nu-scatter absorption fission nu-fission</scores>
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</tally>
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|
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<tally id="2">
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<filter type="cell" bins="100" />
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<filter type="energy" bins="0 20.0" />
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<scores>total scatter nu-scatter absorption fission nu-fission</scores>
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</tally>
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<tally id="3">
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<filter type="cell" bins="100" />
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<filter type="energy" bins="0 20.0" />
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<filter type="energyout" bins="0 20.0" />
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<scores>scatter nu-scatter nu-fission</scores>
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</tally>
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</tallies>
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19
examples/lattice/nested/jeff/materials.xml
Normal file
19
examples/lattice/nested/jeff/materials.xml
Normal file
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@ -0,0 +1,19 @@
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|||
<?xml version="1.0"?>
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<materials>
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||||
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<default_xs>31c</default_xs>
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|
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<!-- Definition of materials -->
|
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<material id="1">
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<density value="4.5" units="g/cc" />
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<nuclide name="U-235" ao="1.0" />
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</material>
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|
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<material id="2">
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<density value="1.0" units="g/cc" />
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<nuclide name="H-1" ao="2.0" />
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<nuclide name="O-16" ao="1.0" />
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<sab name="lwtr01" xs="31t" />
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</material>
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</materials>
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45
examples/lattice/nested/mcnp/geometry.xml
Normal file
45
examples/lattice/nested/mcnp/geometry.xml
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@ -0,0 +1,45 @@
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<?xml version="1.0"?>
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<geometry>
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<cell id="1" fill="6" surfaces="1 -2 3 -4" />
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<cell id="2" universe="5" fill="4" surfaces="1 -2 3 -4" />
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<cell id="101" universe="1" material="1" surfaces="-5" />
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<cell id="102" universe="1" material="2" surfaces="5" />
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<cell id="201" universe="2" material="1" surfaces="-6" />
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<cell id="202" universe="2" material="2" surfaces="6" />
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<cell id="301" universe="3" material="1" surfaces="-7" />
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<cell id="302" universe="3" material="2" surfaces="7" />
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<!-- 4 x 4 assembly -->
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<lattice id="4">
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<type>rectangular</type>
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<dimension>2 2</dimension>
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<lower_left>-1.0 -1.0</lower_left>
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<width>1.0 1.0</width>
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<universes>
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1 2
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2 3
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</universes>
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</lattice>
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<!-- 4 x 4 core -->
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<lattice id="6">
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<type>rectangular</type>
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<dimension>2 2</dimension>
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<lower_left>-2.0 -2.0</lower_left>
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<width>2.0 2.0</width>
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<universes>
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5 5
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5 5
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</universes>
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</lattice>
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<surface id="1" type="x-plane" coeffs="-2.0" boundary="vacuum" />
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<surface id="2" type="x-plane" coeffs="2.0" boundary="vacuum" />
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<surface id="3" type="y-plane" coeffs="-2.0" boundary="vacuum" />
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<surface id="4" type="y-plane" coeffs="2.0" boundary="vacuum" />
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<surface id="5" type="z-cylinder" coeffs="0.0 0.0 0.4" />
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<surface id="6" type="z-cylinder" coeffs="0.0 0.0 0.3" />
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<surface id="7" type="z-cylinder" coeffs="0.0 0.0 0.2" />
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</geometry>
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45
examples/lattice/nested/nndc/geometry.xml
Normal file
45
examples/lattice/nested/nndc/geometry.xml
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@ -0,0 +1,45 @@
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<?xml version="1.0"?>
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<geometry>
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<cell id="1" fill="6" surfaces="1 -2 3 -4" />
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<cell id="2" universe="5" fill="4" surfaces="1 -2 3 -4" />
|
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<cell id="101" universe="1" material="1" surfaces="-5" />
|
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<cell id="102" universe="1" material="2" surfaces="5" />
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<cell id="201" universe="2" material="1" surfaces="-6" />
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<cell id="202" universe="2" material="2" surfaces="6" />
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<cell id="301" universe="3" material="1" surfaces="-7" />
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<cell id="302" universe="3" material="2" surfaces="7" />
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<!-- 4 x 4 assembly -->
|
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<lattice id="4">
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<type>rectangular</type>
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<dimension>2 2</dimension>
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<lower_left>-1.0 -1.0</lower_left>
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<width>1.0 1.0</width>
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<universes>
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1 2
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2 3
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</universes>
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</lattice>
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<!-- 4 x 4 core -->
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<lattice id="6">
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<type>rectangular</type>
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<dimension>2 2</dimension>
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<lower_left>-2.0 -2.0</lower_left>
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<width>2.0 2.0</width>
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<universes>
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5 5
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5 5
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</universes>
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</lattice>
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<surface id="1" type="x-plane" coeffs="-2.0" boundary="vacuum" />
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<surface id="2" type="x-plane" coeffs="2.0" boundary="vacuum" />
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<surface id="3" type="y-plane" coeffs="-2.0" boundary="vacuum" />
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<surface id="4" type="y-plane" coeffs="2.0" boundary="vacuum" />
|
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<surface id="5" type="z-cylinder" coeffs="0.0 0.0 0.4" />
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<surface id="6" type="z-cylinder" coeffs="0.0 0.0 0.3" />
|
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<surface id="7" type="z-cylinder" coeffs="0.0 0.0 0.2" />
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|
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</geometry>
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19
examples/lattice/nested/nndc/materials.xml
Normal file
19
examples/lattice/nested/nndc/materials.xml
Normal file
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@ -0,0 +1,19 @@
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<?xml version="1.0"?>
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<materials>
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|
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<default_xs>71c</default_xs>
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|
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<!-- Definition of materials -->
|
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<material id="1">
|
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<density value="4.5" units="g/cc" />
|
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<nuclide name="U-235" ao="1.0" />
|
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</material>
|
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|
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<material id="2">
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<density value="1.0" units="g/cc" />
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<nuclide name="H-1" ao="2.0" />
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<nuclide name="O-16" ao="1.0" />
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<sab name="HH2O" xs="71t" />
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</material>
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</materials>
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10
examples/lattice/nested/nndc/plots.xml
Normal file
10
examples/lattice/nested/nndc/plots.xml
Normal file
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@ -0,0 +1,10 @@
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<?xml version="1.0"?>
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<plots>
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<plot id="1" color="mat">
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<origin>0. 0. 0.</origin>
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<width>4.0 4.0</width>
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<pixels>400 400</pixels>
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</plot>
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</plots>
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18
examples/lattice/nested/nndc/settings.xml
Normal file
18
examples/lattice/nested/nndc/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
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<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
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<!-- Parameters for k-eigenvalue calculation -->
|
||||
<eigenvalue>
|
||||
<batches>20</batches>
|
||||
<inactive>10</inactive>
|
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<particles>10000</particles>
|
||||
</eigenvalue>
|
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|
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<!-- Starting source -->
|
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<source>
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<space type="box">
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<parameters>-1 -1 -1 1 1 1</parameters>
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</space>
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</source>
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|
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</settings>
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16
examples/lattice/nested/nndc/tallies.xml
Normal file
16
examples/lattice/nested/nndc/tallies.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
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<?xml version="1.0"?>
|
||||
<tallies>
|
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|
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<mesh id="1">
|
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<type>rectangular</type>
|
||||
<dimension>4 4</dimension>
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<lower_left>-2.0 -2.0</lower_left>
|
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<width>1.0 1.0</width>
|
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</mesh>
|
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|
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<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
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<scores>total</scores>
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</tally>
|
||||
|
||||
</tallies>
|
||||
45
examples/lattice/nested/serpent/geometry.xml
Normal file
45
examples/lattice/nested/serpent/geometry.xml
Normal file
|
|
@ -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>
|
||||
<lower_left>-1.0 -1.0</lower_left>
|
||||
<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>
|
||||
<lower_left>-2.0 -2.0</lower_left>
|
||||
<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>
|
||||
19
examples/lattice/nested/serpent/materials.xml
Normal file
19
examples/lattice/nested/serpent/materials.xml
Normal file
|
|
@ -0,0 +1,19 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<default_xs>03c</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="lwe7" xs="00t" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
10
examples/lattice/nested/serpent/plots.xml
Normal file
10
examples/lattice/nested/serpent/plots.xml
Normal 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>
|
||||
18
examples/lattice/nested/serpent/settings.xml
Normal file
18
examples/lattice/nested/serpent/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Parameters for k-eigenvalue calculation -->
|
||||
<eigenvalue>
|
||||
<batches>20</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>10000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- Starting source -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-1 -1 -1 1 1 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
</settings>
|
||||
16
examples/lattice/nested/serpent/tallies.xml
Normal file
16
examples/lattice/nested/serpent/tallies.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<mesh id="1">
|
||||
<type>rectangular</type>
|
||||
<dimension>4 4</dimension>
|
||||
<lower_left>-2.0 -2.0</lower_left>
|
||||
<width>1.0 1.0</width>
|
||||
</mesh>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
||||
<scores>total</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
19
examples/lattice/simple/jeff/materials.xml
Normal file
19
examples/lattice/simple/jeff/materials.xml
Normal file
|
|
@ -0,0 +1,19 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<default_xs>31c</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="lwtr01" xs="31t" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
10
examples/lattice/simple/jeff/plots.xml
Normal file
10
examples/lattice/simple/jeff/plots.xml
Normal 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>
|
||||
18
examples/lattice/simple/jeff/settings.xml
Normal file
18
examples/lattice/simple/jeff/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Parameters for k-eigenvalue calculation -->
|
||||
<eigenvalue>
|
||||
<batches>20</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>10000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- Starting source -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-1 -1 -1 1 1 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
</settings>
|
||||
16
examples/lattice/simple/jeff/tallies.xml
Normal file
16
examples/lattice/simple/jeff/tallies.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<mesh id="1">
|
||||
<type>rectangular</type>
|
||||
<dimension>4 4</dimension>
|
||||
<lower_left>-2.0 -2.0</lower_left>
|
||||
<width>1.0 1.0</width>
|
||||
</mesh>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
||||
<scores>total</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
33
examples/lattice/simple/mcnp/geometry.xml
Normal file
33
examples/lattice/simple/mcnp/geometry.xml
Normal file
|
|
@ -0,0 +1,33 @@
|
|||
<?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>
|
||||
<lower_left>-2.0 -2.0</lower_left>
|
||||
<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>
|
||||
10
examples/lattice/simple/mcnp/plots.xml
Normal file
10
examples/lattice/simple/mcnp/plots.xml
Normal 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>
|
||||
18
examples/lattice/simple/mcnp/settings.xml
Normal file
18
examples/lattice/simple/mcnp/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Parameters for k-eigenvalue calculation -->
|
||||
<eigenvalue>
|
||||
<batches>20</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>10000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- Starting source -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-1 -1 -1 1 1 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
</settings>
|
||||
16
examples/lattice/simple/mcnp/tallies.xml
Normal file
16
examples/lattice/simple/mcnp/tallies.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<mesh id="1">
|
||||
<type>rectangular</type>
|
||||
<dimension>4 4</dimension>
|
||||
<lower_left>-2.0 -2.0</lower_left>
|
||||
<width>1.0 1.0</width>
|
||||
</mesh>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
||||
<scores>total</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
33
examples/lattice/simple/nndc/geometry.xml
Normal file
33
examples/lattice/simple/nndc/geometry.xml
Normal file
|
|
@ -0,0 +1,33 @@
|
|||
<?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>
|
||||
<lower_left>-2.0 -2.0</lower_left>
|
||||
<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>
|
||||
19
examples/lattice/simple/nndc/materials.xml
Normal file
19
examples/lattice/simple/nndc/materials.xml
Normal file
|
|
@ -0,0 +1,19 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<default_xs>71c</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="HH2O" xs="71t" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
10
examples/lattice/simple/nndc/plots.xml
Normal file
10
examples/lattice/simple/nndc/plots.xml
Normal 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>
|
||||
18
examples/lattice/simple/nndc/settings.xml
Normal file
18
examples/lattice/simple/nndc/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Parameters for k-eigenvalue calculation -->
|
||||
<eigenvalue>
|
||||
<batches>20</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>10000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- Starting source -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-1 -1 -1 1 1 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
</settings>
|
||||
16
examples/lattice/simple/nndc/tallies.xml
Normal file
16
examples/lattice/simple/nndc/tallies.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<mesh id="1">
|
||||
<type>rectangular</type>
|
||||
<dimension>4 4</dimension>
|
||||
<lower_left>-2.0 -2.0</lower_left>
|
||||
<width>1.0 1.0</width>
|
||||
</mesh>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
||||
<scores>total</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
33
examples/lattice/simple/serpent/geometry.xml
Normal file
33
examples/lattice/simple/serpent/geometry.xml
Normal file
|
|
@ -0,0 +1,33 @@
|
|||
<?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>
|
||||
<lower_left>-2.0 -2.0</lower_left>
|
||||
<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>
|
||||
19
examples/lattice/simple/serpent/materials.xml
Normal file
19
examples/lattice/simple/serpent/materials.xml
Normal file
|
|
@ -0,0 +1,19 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<default_xs>03c</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="lwe7" xs="00t" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
10
examples/lattice/simple/serpent/plots.xml
Normal file
10
examples/lattice/simple/serpent/plots.xml
Normal 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>
|
||||
18
examples/lattice/simple/serpent/settings.xml
Normal file
18
examples/lattice/simple/serpent/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Parameters for k-eigenvalue calculation -->
|
||||
<eigenvalue>
|
||||
<batches>20</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>10000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- Starting source -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-1 -1 -1 1 1 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
</settings>
|
||||
16
examples/lattice/simple/serpent/tallies.xml
Normal file
16
examples/lattice/simple/serpent/tallies.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<mesh id="1">
|
||||
<type>rectangular</type>
|
||||
<dimension>4 4</dimension>
|
||||
<lower_left>-2.0 -2.0</lower_left>
|
||||
<width>1.0 1.0</width>
|
||||
</mesh>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
||||
<scores>total</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
70
examples/pincell/jeff/materials.xml
Normal file
70
examples/pincell/jeff/materials.xml
Normal file
|
|
@ -0,0 +1,70 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<!-- By default, use 300K cross sections -->
|
||||
<default_xs>31c</default_xs>
|
||||
|
||||
<!--
|
||||
Since O-18 is not present in ENDF/B-VII, it was necessary to combine the
|
||||
atom densities for O-17 and O-18 in any materials containing Oxygen.
|
||||
-->
|
||||
|
||||
<!-- UO2 fuel at 2.4 wt% enrichment -->
|
||||
<material id="1">
|
||||
<density value="10.29769" units="g/cm3" />
|
||||
<nuclide name="U-234" ao="4.4843e-06" />
|
||||
<nuclide name="U-235" ao="5.5815e-04" />
|
||||
<nuclide name="U-238" ao="2.2408e-02" />
|
||||
<nuclide name="O-16" ao="4.5829e-02" />
|
||||
<nuclide name="O-17" ao="1.1164e-04" />
|
||||
</material>
|
||||
|
||||
<!-- Helium for gap -->
|
||||
<material id="2">
|
||||
<density value="0.001598" units="g/cm3" />
|
||||
<nuclide name="He-4" ao="2.4044e-04" />
|
||||
</material>
|
||||
|
||||
<!-- Zircaloy 4 -->
|
||||
<material id="3">
|
||||
<density value="6.55" units="g/cm3" />
|
||||
<nuclide name="O-16" ao="3.0743e-04" />
|
||||
<nuclide name="O-17" ao="7.4887e-07" />
|
||||
<nuclide name="Cr-50" ao="3.2962e-06" />
|
||||
<nuclide name="Cr-52" ao="6.3564e-05" />
|
||||
<nuclide name="Cr-53" ao="7.2076e-06" />
|
||||
<nuclide name="Cr-54" ao="1.7941e-06" />
|
||||
<nuclide name="Fe-54" ao="8.6699e-06" />
|
||||
<nuclide name="Fe-56" ao="1.3610e-04" />
|
||||
<nuclide name="Fe-57" ao="3.1431e-06" />
|
||||
<nuclide name="Fe-58" ao="4.1829e-07" />
|
||||
<nuclide name="Zr-90" ao="2.1827e-02" />
|
||||
<nuclide name="Zr-91" ao="4.7600e-03" />
|
||||
<nuclide name="Zr-92" ao="7.2758e-03" />
|
||||
<nuclide name="Zr-94" ao="7.3734e-03" />
|
||||
<nuclide name="Zr-96" ao="1.1879e-03" />
|
||||
<nuclide name="Sn-112" ao="4.6735e-06" />
|
||||
<nuclide name="Sn-114" ao="3.1799e-06" />
|
||||
<nuclide name="Sn-115" ao="1.6381e-06" />
|
||||
<nuclide name="Sn-116" ao="7.0055e-05" />
|
||||
<nuclide name="Sn-117" ao="3.7003e-05" />
|
||||
<nuclide name="Sn-118" ao="1.1669e-04" />
|
||||
<nuclide name="Sn-119" ao="4.1387e-05" />
|
||||
<nuclide name="Sn-120" ao="1.5697e-04" />
|
||||
<nuclide name="Sn-122" ao="2.2308e-05" />
|
||||
<nuclide name="Sn-124" ao="2.7897e-05" />
|
||||
</material>
|
||||
|
||||
<!-- Borated water at 975 ppm -->
|
||||
<material id="4">
|
||||
<density value="0.740582" units="g/cm3" />
|
||||
<nuclide name="B-10" ao="8.0042e-06" />
|
||||
<nuclide name="B-11" ao="3.2218e-05" />
|
||||
<nuclide name="H-1" ao="4.9457e-02" />
|
||||
<nuclide name="H-2" ao="7.4196e-06" />
|
||||
<nuclide name="O-16" ao="2.4672e-02" />
|
||||
<nuclide name="O-17" ao="6.0099e-05" />
|
||||
<sab name="lwtr01" xs="31t" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
27
examples/pincell/mcnp/geometry.xml
Normal file
27
examples/pincell/mcnp/geometry.xml
Normal file
|
|
@ -0,0 +1,27 @@
|
|||
<?xml version="1.0"?>
|
||||
<geometry>
|
||||
|
||||
<!--
|
||||
This is a simple pin cell model based on dimensions from the MIT BEAVRS
|
||||
(Benchmarking for Evaluation and Validation of Reactor Simulations)
|
||||
benchmark.
|
||||
-->
|
||||
|
||||
<!-- Surfaces for fuel, gap, cladding. Dimensions from Figure 2 in BEAVRS -->
|
||||
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.39218" /> <!-- Fuel OR -->
|
||||
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.40005" /> <!-- Clad IR -->
|
||||
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.45720" /> <!-- Clad OR -->
|
||||
|
||||
<!-- Reflective surfaces on outside of pin-cell. The lattice pitch is 1.25984
|
||||
cm (taken from Table 2 in BEAVRS). -->
|
||||
<surface id="4" type="x-plane" coeffs="-0.62992" boundary="reflective" />
|
||||
<surface id="5" type="x-plane" coeffs=" 0.62992" boundary="reflective" />
|
||||
<surface id="6" type="y-plane" coeffs="-0.62992" boundary="reflective" />
|
||||
<surface id="7" type="y-plane" coeffs=" 0.62992" boundary="reflective" />
|
||||
|
||||
<cell id="1" material="1" surfaces=" -1" /> <!-- UO2 Fuel -->
|
||||
<cell id="2" material="2" surfaces="1 -2" /> <!-- Helium gap -->
|
||||
<cell id="3" material="3" surfaces="2 -3" /> <!-- Zircaloy cladding -->
|
||||
<cell id="4" material="4" surfaces="3 4 -5 6 -7" /> <!-- Borated water -->
|
||||
|
||||
</geometry>
|
||||
70
examples/pincell/mcnp/materials.xml
Normal file
70
examples/pincell/mcnp/materials.xml
Normal file
|
|
@ -0,0 +1,70 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<!-- By default, use 300K cross sections -->
|
||||
<default_xs>70c</default_xs>
|
||||
|
||||
<!--
|
||||
Since O-18 is not present in ENDF/B-VII, it was necessary to combine the
|
||||
atom densities for O-17 and O-18 in any materials containing Oxygen.
|
||||
-->
|
||||
|
||||
<!-- UO2 fuel at 2.4 wt% enrichment -->
|
||||
<material id="1">
|
||||
<density value="10.29769" units="g/cm3" />
|
||||
<nuclide name="U-234" ao="4.4843e-06" />
|
||||
<nuclide name="U-235" ao="5.5815e-04" />
|
||||
<nuclide name="U-238" ao="2.2408e-02" />
|
||||
<nuclide name="O-16" ao="4.5829e-02" />
|
||||
<nuclide name="O-17" ao="1.1164e-04" />
|
||||
</material>
|
||||
|
||||
<!-- Helium for gap -->
|
||||
<material id="2">
|
||||
<density value="0.001598" units="g/cm3" />
|
||||
<nuclide name="He-4" ao="2.4044e-04" />
|
||||
</material>
|
||||
|
||||
<!-- Zircaloy 4 -->
|
||||
<material id="3">
|
||||
<density value="6.55" units="g/cm3" />
|
||||
<nuclide name="O-16" ao="3.0743e-04" />
|
||||
<nuclide name="O-17" ao="7.4887e-07" />
|
||||
<nuclide name="Cr-50" ao="3.2962e-06" />
|
||||
<nuclide name="Cr-52" ao="6.3564e-05" />
|
||||
<nuclide name="Cr-53" ao="7.2076e-06" />
|
||||
<nuclide name="Cr-54" ao="1.7941e-06" />
|
||||
<nuclide name="Fe-54" ao="8.6699e-06" />
|
||||
<nuclide name="Fe-56" ao="1.3610e-04" />
|
||||
<nuclide name="Fe-57" ao="3.1431e-06" />
|
||||
<nuclide name="Fe-58" ao="4.1829e-07" />
|
||||
<nuclide name="Zr-90" ao="2.1827e-02" />
|
||||
<nuclide name="Zr-91" ao="4.7600e-03" />
|
||||
<nuclide name="Zr-92" ao="7.2758e-03" />
|
||||
<nuclide name="Zr-94" ao="7.3734e-03" />
|
||||
<nuclide name="Zr-96" ao="1.1879e-03" />
|
||||
<nuclide name="Sn-112" ao="4.6735e-06" />
|
||||
<nuclide name="Sn-114" ao="3.1799e-06" />
|
||||
<nuclide name="Sn-115" ao="1.6381e-06" />
|
||||
<nuclide name="Sn-116" ao="7.0055e-05" />
|
||||
<nuclide name="Sn-117" ao="3.7003e-05" />
|
||||
<nuclide name="Sn-118" ao="1.1669e-04" />
|
||||
<nuclide name="Sn-119" ao="4.1387e-05" />
|
||||
<nuclide name="Sn-120" ao="1.5697e-04" />
|
||||
<nuclide name="Sn-122" ao="2.2308e-05" />
|
||||
<nuclide name="Sn-124" ao="2.7897e-05" />
|
||||
</material>
|
||||
|
||||
<!-- Borated water at 975 ppm -->
|
||||
<material id="4">
|
||||
<density value="0.740582" units="g/cm3" />
|
||||
<nuclide name="B-10" ao="8.0042e-06" />
|
||||
<nuclide name="B-11" ao="3.2218e-05" />
|
||||
<nuclide name="H-1" ao="4.9457e-02" />
|
||||
<nuclide name="H-2" ao="7.4196e-06" />
|
||||
<nuclide name="O-16" ao="2.4672e-02" />
|
||||
<nuclide name="O-17" ao="6.0099e-05" />
|
||||
<sab name="lwtr" xs="10t" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
32
examples/pincell/mcnp/settings.xml
Normal file
32
examples/pincell/mcnp/settings.xml
Normal file
|
|
@ -0,0 +1,32 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Define how many particles to run and for how many batches -->
|
||||
<eigenvalue>
|
||||
<batches>100</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>1000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- The starting source is a uniform distribution over the entire pin
|
||||
cell. Note that since this is effectively a 2D model, the z coordinates
|
||||
are inconsequential -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>
|
||||
-0.62992 -0.62992 -1.
|
||||
0.62992 0.62992 1.
|
||||
</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
<!-- To assess convergence of the source distribution, we need to define the
|
||||
bounds for a mesh over which the Shannon entropy should be
|
||||
calculated. The extent in the z direction is made arbitrarily large. -->
|
||||
<entropy>
|
||||
<lower_left>-0.39218 -0.39218 -1.e50</lower_left>
|
||||
<upper_right>0.39218 0.39218 1.e50</upper_right>
|
||||
<dimension>10 10 1</dimension>
|
||||
</entropy>
|
||||
|
||||
</settings>
|
||||
16
examples/pincell/mcnp/tallies.xml
Normal file
16
examples/pincell/mcnp/tallies.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<mesh id="1" type="rectangular">
|
||||
<dimension>100 100 1</dimension>
|
||||
<lower_left>-0.62992 -0.62992 -1.e50</lower_left>
|
||||
<upper_right>0.62992 0.62992 1.e50</upper_right>
|
||||
</mesh>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
||||
<filter type="energy" bins="0. 4.e-6 20.0" />
|
||||
<scores>flux fission nu-fission</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
27
examples/pincell/nndc/geometry.xml
Normal file
27
examples/pincell/nndc/geometry.xml
Normal file
|
|
@ -0,0 +1,27 @@
|
|||
<?xml version="1.0"?>
|
||||
<geometry>
|
||||
|
||||
<!--
|
||||
This is a simple pin cell model based on dimensions from the MIT BEAVRS
|
||||
(Benchmarking for Evaluation and Validation of Reactor Simulations)
|
||||
benchmark.
|
||||
-->
|
||||
|
||||
<!-- Surfaces for fuel, gap, cladding. Dimensions from Figure 2 in BEAVRS -->
|
||||
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.39218" /> <!-- Fuel OR -->
|
||||
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.40005" /> <!-- Clad IR -->
|
||||
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.45720" /> <!-- Clad OR -->
|
||||
|
||||
<!-- Reflective surfaces on outside of pin-cell. The lattice pitch is 1.25984
|
||||
cm (taken from Table 2 in BEAVRS). -->
|
||||
<surface id="4" type="x-plane" coeffs="-0.62992" boundary="reflective" />
|
||||
<surface id="5" type="x-plane" coeffs=" 0.62992" boundary="reflective" />
|
||||
<surface id="6" type="y-plane" coeffs="-0.62992" boundary="reflective" />
|
||||
<surface id="7" type="y-plane" coeffs=" 0.62992" boundary="reflective" />
|
||||
|
||||
<cell id="1" material="1" surfaces=" -1" /> <!-- UO2 Fuel -->
|
||||
<cell id="2" material="2" surfaces="1 -2" /> <!-- Helium gap -->
|
||||
<cell id="3" material="3" surfaces="2 -3" /> <!-- Zircaloy cladding -->
|
||||
<cell id="4" material="4" surfaces="3 4 -5 6 -7" /> <!-- Borated water -->
|
||||
|
||||
</geometry>
|
||||
|
|
@ -1,7 +1,7 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<!-- By default, use 600K cross sections -->
|
||||
<!-- By default, use 300K cross sections -->
|
||||
<default_xs>71c</default_xs>
|
||||
|
||||
<!--
|
||||
|
|
@ -64,7 +64,7 @@
|
|||
<nuclide name="H-2" ao="7.4196e-06" />
|
||||
<nuclide name="O-16" ao="2.4672e-02" />
|
||||
<nuclide name="O-17" ao="6.0099e-05" />
|
||||
<sab name="lwtr" xs="15t" />
|
||||
<sab name="HH2O" xs="71t" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
</materials>
|
||||
32
examples/pincell/nndc/settings.xml
Normal file
32
examples/pincell/nndc/settings.xml
Normal file
|
|
@ -0,0 +1,32 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Define how many particles to run and for how many batches -->
|
||||
<eigenvalue>
|
||||
<batches>100</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>1000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- The starting source is a uniform distribution over the entire pin
|
||||
cell. Note that since this is effectively a 2D model, the z coordinates
|
||||
are inconsequential -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>
|
||||
-0.62992 -0.62992 -1.
|
||||
0.62992 0.62992 1.
|
||||
</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
<!-- To assess convergence of the source distribution, we need to define the
|
||||
bounds for a mesh over which the Shannon entropy should be
|
||||
calculated. The extent in the z direction is made arbitrarily large. -->
|
||||
<entropy>
|
||||
<lower_left>-0.39218 -0.39218 -1.e50</lower_left>
|
||||
<upper_right>0.39218 0.39218 1.e50</upper_right>
|
||||
<dimension>10 10 1</dimension>
|
||||
</entropy>
|
||||
|
||||
</settings>
|
||||
16
examples/pincell/nndc/tallies.xml
Normal file
16
examples/pincell/nndc/tallies.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<mesh id="1" type="rectangular">
|
||||
<dimension>100 100 1</dimension>
|
||||
<lower_left>-0.62992 -0.62992 -1.e50</lower_left>
|
||||
<upper_right>0.62992 0.62992 1.e50</upper_right>
|
||||
</mesh>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
||||
<filter type="energy" bins="0. 4.e-6 20.0" />
|
||||
<scores>flux fission nu-fission</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
27
examples/pincell/serpent/geometry.xml
Normal file
27
examples/pincell/serpent/geometry.xml
Normal file
|
|
@ -0,0 +1,27 @@
|
|||
<?xml version="1.0"?>
|
||||
<geometry>
|
||||
|
||||
<!--
|
||||
This is a simple pin cell model based on dimensions from the MIT BEAVRS
|
||||
(Benchmarking for Evaluation and Validation of Reactor Simulations)
|
||||
benchmark.
|
||||
-->
|
||||
|
||||
<!-- Surfaces for fuel, gap, cladding. Dimensions from Figure 2 in BEAVRS -->
|
||||
<surface id="1" type="z-cylinder" coeffs="0. 0. 0.39218" /> <!-- Fuel OR -->
|
||||
<surface id="2" type="z-cylinder" coeffs="0. 0. 0.40005" /> <!-- Clad IR -->
|
||||
<surface id="3" type="z-cylinder" coeffs="0. 0. 0.45720" /> <!-- Clad OR -->
|
||||
|
||||
<!-- Reflective surfaces on outside of pin-cell. The lattice pitch is 1.25984
|
||||
cm (taken from Table 2 in BEAVRS). -->
|
||||
<surface id="4" type="x-plane" coeffs="-0.62992" boundary="reflective" />
|
||||
<surface id="5" type="x-plane" coeffs=" 0.62992" boundary="reflective" />
|
||||
<surface id="6" type="y-plane" coeffs="-0.62992" boundary="reflective" />
|
||||
<surface id="7" type="y-plane" coeffs=" 0.62992" boundary="reflective" />
|
||||
|
||||
<cell id="1" material="1" surfaces=" -1" /> <!-- UO2 Fuel -->
|
||||
<cell id="2" material="2" surfaces="1 -2" /> <!-- Helium gap -->
|
||||
<cell id="3" material="3" surfaces="2 -3" /> <!-- Zircaloy cladding -->
|
||||
<cell id="4" material="4" surfaces="3 4 -5 6 -7" /> <!-- Borated water -->
|
||||
|
||||
</geometry>
|
||||
70
examples/pincell/serpent/materials.xml
Normal file
70
examples/pincell/serpent/materials.xml
Normal file
|
|
@ -0,0 +1,70 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<!-- By default, use 300K cross sections -->
|
||||
<default_xs>03c</default_xs>
|
||||
|
||||
<!--
|
||||
Since O-18 is not present in ENDF/B-VII, it was necessary to combine the
|
||||
atom densities for O-17 and O-18 in any materials containing Oxygen.
|
||||
-->
|
||||
|
||||
<!-- UO2 fuel at 2.4 wt% enrichment -->
|
||||
<material id="1">
|
||||
<density value="10.29769" units="g/cm3" />
|
||||
<nuclide name="U-234" ao="4.4843e-06" />
|
||||
<nuclide name="U-235" ao="5.5815e-04" />
|
||||
<nuclide name="U-238" ao="2.2408e-02" />
|
||||
<nuclide name="O-16" ao="4.5829e-02" />
|
||||
<nuclide name="O-17" ao="1.1164e-04" />
|
||||
</material>
|
||||
|
||||
<!-- Helium for gap -->
|
||||
<material id="2">
|
||||
<density value="0.001598" units="g/cm3" />
|
||||
<nuclide name="He-4" ao="2.4044e-04" />
|
||||
</material>
|
||||
|
||||
<!-- Zircaloy 4 -->
|
||||
<material id="3">
|
||||
<density value="6.55" units="g/cm3" />
|
||||
<nuclide name="O-16" ao="3.0743e-04" />
|
||||
<nuclide name="O-17" ao="7.4887e-07" />
|
||||
<nuclide name="Cr-50" ao="3.2962e-06" />
|
||||
<nuclide name="Cr-52" ao="6.3564e-05" />
|
||||
<nuclide name="Cr-53" ao="7.2076e-06" />
|
||||
<nuclide name="Cr-54" ao="1.7941e-06" />
|
||||
<nuclide name="Fe-54" ao="8.6699e-06" />
|
||||
<nuclide name="Fe-56" ao="1.3610e-04" />
|
||||
<nuclide name="Fe-57" ao="3.1431e-06" />
|
||||
<nuclide name="Fe-58" ao="4.1829e-07" />
|
||||
<nuclide name="Zr-90" ao="2.1827e-02" />
|
||||
<nuclide name="Zr-91" ao="4.7600e-03" />
|
||||
<nuclide name="Zr-92" ao="7.2758e-03" />
|
||||
<nuclide name="Zr-94" ao="7.3734e-03" />
|
||||
<nuclide name="Zr-96" ao="1.1879e-03" />
|
||||
<nuclide name="Sn-112" ao="4.6735e-06" />
|
||||
<nuclide name="Sn-114" ao="3.1799e-06" />
|
||||
<nuclide name="Sn-115" ao="1.6381e-06" />
|
||||
<nuclide name="Sn-116" ao="7.0055e-05" />
|
||||
<nuclide name="Sn-117" ao="3.7003e-05" />
|
||||
<nuclide name="Sn-118" ao="1.1669e-04" />
|
||||
<nuclide name="Sn-119" ao="4.1387e-05" />
|
||||
<nuclide name="Sn-120" ao="1.5697e-04" />
|
||||
<nuclide name="Sn-122" ao="2.2308e-05" />
|
||||
<nuclide name="Sn-124" ao="2.7897e-05" />
|
||||
</material>
|
||||
|
||||
<!-- Borated water at 975 ppm -->
|
||||
<material id="4">
|
||||
<density value="0.740582" units="g/cm3" />
|
||||
<nuclide name="B-10" ao="8.0042e-06" />
|
||||
<nuclide name="B-11" ao="3.2218e-05" />
|
||||
<nuclide name="H-1" ao="4.9457e-02" />
|
||||
<nuclide name="H-2" ao="7.4196e-06" />
|
||||
<nuclide name="O-16" ao="2.4672e-02" />
|
||||
<nuclide name="O-17" ao="6.0099e-05" />
|
||||
<sab name="lwe7" xs="00t" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
32
examples/pincell/serpent/settings.xml
Normal file
32
examples/pincell/serpent/settings.xml
Normal file
|
|
@ -0,0 +1,32 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Define how many particles to run and for how many batches -->
|
||||
<eigenvalue>
|
||||
<batches>100</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>1000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- The starting source is a uniform distribution over the entire pin
|
||||
cell. Note that since this is effectively a 2D model, the z coordinates
|
||||
are inconsequential -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>
|
||||
-0.62992 -0.62992 -1.
|
||||
0.62992 0.62992 1.
|
||||
</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
<!-- To assess convergence of the source distribution, we need to define the
|
||||
bounds for a mesh over which the Shannon entropy should be
|
||||
calculated. The extent in the z direction is made arbitrarily large. -->
|
||||
<entropy>
|
||||
<lower_left>-0.39218 -0.39218 -1.e50</lower_left>
|
||||
<upper_right>0.39218 0.39218 1.e50</upper_right>
|
||||
<dimension>10 10 1</dimension>
|
||||
</entropy>
|
||||
|
||||
</settings>
|
||||
16
examples/pincell/serpent/tallies.xml
Normal file
16
examples/pincell/serpent/tallies.xml
Normal file
|
|
@ -0,0 +1,16 @@
|
|||
<?xml version="1.0"?>
|
||||
<tallies>
|
||||
|
||||
<mesh id="1" type="rectangular">
|
||||
<dimension>100 100 1</dimension>
|
||||
<lower_left>-0.62992 -0.62992 -1.e50</lower_left>
|
||||
<upper_right>0.62992 0.62992 1.e50</upper_right>
|
||||
</mesh>
|
||||
|
||||
<tally id="1">
|
||||
<filter type="mesh" bins="1" />
|
||||
<filter type="energy" bins="0. 4.e-6 20.0" />
|
||||
<scores>flux fission nu-fission</scores>
|
||||
</tally>
|
||||
|
||||
</tallies>
|
||||
11
examples/reflective/jeff/materials.xml
Normal file
11
examples/reflective/jeff/materials.xml
Normal file
|
|
@ -0,0 +1,11 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<default_xs>31c</default_xs>
|
||||
|
||||
<material id="1">
|
||||
<density value="4.5" units="g/cc" />
|
||||
<nuclide name="U-235" ao="1.0" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
19
examples/reflective/mcnp/geometry.xml
Normal file
19
examples/reflective/mcnp/geometry.xml
Normal file
|
|
@ -0,0 +1,19 @@
|
|||
<?xml version="1.0"?>
|
||||
<geometry>
|
||||
|
||||
<!-- Definition of Cells -->
|
||||
<cell id="1">
|
||||
<universe>0</universe>
|
||||
<material>1</material>
|
||||
<surfaces>1 -2 3 -4 5 -6</surfaces>
|
||||
</cell>
|
||||
|
||||
<!-- Defition of Surfaces -->
|
||||
<surface id="1" type="x-plane" coeffs="-1" boundary="vacuum" />
|
||||
<surface id="2" type="x-plane" coeffs="1" boundary="vacuum" />
|
||||
<surface id="3" type="y-plane" coeffs="-1" boundary="reflective" />
|
||||
<surface id="4" type="y-plane" coeffs="1" boundary="reflective" />
|
||||
<surface id="5" type="z-plane" coeffs="-1" boundary="reflective" />
|
||||
<surface id="6" type="z-plane" coeffs="1" boundary="reflective" />
|
||||
|
||||
</geometry>
|
||||
18
examples/reflective/mcnp/settings.xml
Normal file
18
examples/reflective/mcnp/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Parameters for k-eigenvalue calculation -->
|
||||
<eigenvalue>
|
||||
<batches>500</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>10000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- Starting source -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-1 -1 -1 1 1 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
</settings>
|
||||
19
examples/reflective/nndc/geometry.xml
Normal file
19
examples/reflective/nndc/geometry.xml
Normal file
|
|
@ -0,0 +1,19 @@
|
|||
<?xml version="1.0"?>
|
||||
<geometry>
|
||||
|
||||
<!-- Definition of Cells -->
|
||||
<cell id="1">
|
||||
<universe>0</universe>
|
||||
<material>1</material>
|
||||
<surfaces>1 -2 3 -4 5 -6</surfaces>
|
||||
</cell>
|
||||
|
||||
<!-- Defition of Surfaces -->
|
||||
<surface id="1" type="x-plane" coeffs="-1" boundary="vacuum" />
|
||||
<surface id="2" type="x-plane" coeffs="1" boundary="vacuum" />
|
||||
<surface id="3" type="y-plane" coeffs="-1" boundary="reflective" />
|
||||
<surface id="4" type="y-plane" coeffs="1" boundary="reflective" />
|
||||
<surface id="5" type="z-plane" coeffs="-1" boundary="reflective" />
|
||||
<surface id="6" type="z-plane" coeffs="1" boundary="reflective" />
|
||||
|
||||
</geometry>
|
||||
11
examples/reflective/nndc/materials.xml
Normal file
11
examples/reflective/nndc/materials.xml
Normal file
|
|
@ -0,0 +1,11 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<default_xs>71c</default_xs>
|
||||
|
||||
<material id="1">
|
||||
<density value="4.5" units="g/cc" />
|
||||
<nuclide name="U-235" ao="1.0" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
18
examples/reflective/nndc/settings.xml
Normal file
18
examples/reflective/nndc/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Parameters for k-eigenvalue calculation -->
|
||||
<eigenvalue>
|
||||
<batches>500</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>10000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- Starting source -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-1 -1 -1 1 1 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
</settings>
|
||||
19
examples/reflective/serpent/geometry.xml
Normal file
19
examples/reflective/serpent/geometry.xml
Normal file
|
|
@ -0,0 +1,19 @@
|
|||
<?xml version="1.0"?>
|
||||
<geometry>
|
||||
|
||||
<!-- Definition of Cells -->
|
||||
<cell id="1">
|
||||
<universe>0</universe>
|
||||
<material>1</material>
|
||||
<surfaces>1 -2 3 -4 5 -6</surfaces>
|
||||
</cell>
|
||||
|
||||
<!-- Defition of Surfaces -->
|
||||
<surface id="1" type="x-plane" coeffs="-1" boundary="vacuum" />
|
||||
<surface id="2" type="x-plane" coeffs="1" boundary="vacuum" />
|
||||
<surface id="3" type="y-plane" coeffs="-1" boundary="reflective" />
|
||||
<surface id="4" type="y-plane" coeffs="1" boundary="reflective" />
|
||||
<surface id="5" type="z-plane" coeffs="-1" boundary="reflective" />
|
||||
<surface id="6" type="z-plane" coeffs="1" boundary="reflective" />
|
||||
|
||||
</geometry>
|
||||
11
examples/reflective/serpent/materials.xml
Normal file
11
examples/reflective/serpent/materials.xml
Normal file
|
|
@ -0,0 +1,11 @@
|
|||
<?xml version="1.0"?>
|
||||
<materials>
|
||||
|
||||
<default_xs>03c</default_xs>
|
||||
|
||||
<material id="1">
|
||||
<density value="4.5" units="g/cc" />
|
||||
<nuclide name="U-235" ao="1.0" />
|
||||
</material>
|
||||
|
||||
</materials>
|
||||
18
examples/reflective/serpent/settings.xml
Normal file
18
examples/reflective/serpent/settings.xml
Normal file
|
|
@ -0,0 +1,18 @@
|
|||
<?xml version="1.0"?>
|
||||
<settings>
|
||||
|
||||
<!-- Parameters for k-eigenvalue calculation -->
|
||||
<eigenvalue>
|
||||
<batches>500</batches>
|
||||
<inactive>10</inactive>
|
||||
<particles>10000</particles>
|
||||
</eigenvalue>
|
||||
|
||||
<!-- Starting source -->
|
||||
<source>
|
||||
<space type="box">
|
||||
<parameters>-1 -1 -1 1 1 1</parameters>
|
||||
</space>
|
||||
</source>
|
||||
|
||||
</settings>
|
||||
Loading…
Add table
Add a link
Reference in a new issue