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adding back files to be reviewed

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This commit is contained in:
Paul Romano 2019-10-28 11:55:45 -05:00
parent ae28233110
commit bc09d1ef55
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15
examples/xml/basic/geometry.xml Normal file
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<?xml version="1.0"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1" universe="0" fill="37" region="-2" />
<cell id="100" universe="37" material="40" region="-1" />
<cell id="101" universe="37" material="41" region="1" />
<cell id="2" universe="0" material="41" region="2 -3" />
<!-- Defition of Surfaces -->
<surface id="1" type="z-cylinder" coeffs="0 0 7" />
<surface id="2" type="z-cylinder" coeffs="0 0 9" />
<surface id="3" type="z-cylinder" coeffs="0 0 11" boundary="vacuum" />
</geometry>

16
examples/xml/basic/materials.xml Normal file
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<?xml version="1.0"?>
<materials>
<material id="40">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="41">
<density value="1.0" units="g/cc" />
<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
<sab name="c_H_in_H2O"/>
</material>
</materials>

16
examples/xml/basic/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<run_mode>eigenvalue</run_mode>
<batches>15</batches>
<inactive>5</inactive>
<particles>10000</particles>
<!-- Starting source -->
<source>
<space type="box">
<parameters>-4 -4 -4 4 4 4</parameters>
</space>
</source>
</settings>

31
examples/xml/basic/tallies.xml Normal file
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<?xml version="1.0"?>
<tallies>
<filter id="1" type="cell">
<bins>100</bins>
</filter>
<filter id="2" type="energy">
<bins>0 20.0e6</bins>
</filter>
<filter id="3" type="energyout">
<bins>0 20.0e6</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total scatter nu-scatter absorption fission nu-fission</scores>
</tally>
<tally id="2">
<filters>1 2</filters>
<scores>total scatter nu-scatter absorption fission nu-fission</scores>
</tally>
<tally id="3">
<filters>1 2 3</filters>
<scores>scatter nu-scatter nu-fission</scores>
</tally>
</tallies>

39
examples/xml/boxes/geometry.xml Normal file
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<?xml version="1.0"?>
<geometry>
<!--
This example consists of three nested boxes, and is meant to show how to
use Boolean operators to construct complex cell regions.
-->
<surface id="1" type="x-plane" coeffs="-10" boundary="vacuum" />
<surface id="2" type="x-plane" coeffs="-7" />
<surface id="3" type="x-plane" coeffs="-4" />
<surface id="4" type="x-plane" coeffs="4" />
<surface id="5" type="x-plane" coeffs="7" />
<surface id="6" type="x-plane" coeffs="10" boundary="vacuum" />
<surface id="11" type="y-plane" coeffs="-10" boundary="vacuum" />
<surface id="12" type="y-plane" coeffs="-7" />
<surface id="13" type="y-plane" coeffs="-4" />
<surface id="14" type="y-plane" coeffs="4" />
<surface id="15" type="y-plane" coeffs="7" />
<surface id="16" type="y-plane" coeffs="10" boundary="vacuum" />
<surface id="21" type="z-plane" coeffs="-10" boundary="vacuum" />
<surface id="22" type="z-plane" coeffs="-7" />
<surface id="23" type="z-plane" coeffs="-4" />
<surface id="24" type="z-plane" coeffs="4" />
<surface id="25" type="z-plane" coeffs="7" />
<surface id="26" type="z-plane" coeffs="10" boundary="vacuum" />
<!-- Innermost cube -->
<cell id="1" material="1" region="3 -4 13 -14 23 -24" />
<!-- Middle cubic shell -->
<cell id="2" material="2" region="2 -5 12 -15 22 -25 (-3 | 4 | -13 | 14 | -23 | 24)" />
<!-- Outermost cubic shell -->
<cell id="3" material="3" region="1 -6 11 -16 21 -26 ~(2 -5 12 -15 22 -25)" />
</geometry>

21
examples/xml/boxes/materials.xml Normal file
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<?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>
<material id="3">
<density value="1.0" units="g/cc" />
<nuclide name="O16" ao="1.0" />
<nuclide name="H1" ao="2.0" />
<sab name="c_H_in_H2O" />
</material>
</materials>

9
examples/xml/boxes/plots.xml Normal file
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<?xml version="1.0"?>
<plots>
<plot id="1" type="slice">
<color_by>cell</color_by>
<origin>0. 0. 0.</origin>
<width>20. 20.</width>
<pixels>200 200</pixels>
</plot>
</plots>

15
examples/xml/boxes/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<!-- Parameters for k-eigenvalue calculation -->
<run_mode>eigenvalue</run_mode>
<batches>15</batches>
<inactive>5</inactive>
<particles>10000</particles>
<!-- Starting source -->
<source>
<space type="box" parameters="-10. -10. -10. 10. 10. 10." />
</source>
</settings>

43
examples/xml/lattice/nested/geometry.xml Normal file
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<?xml version="1.0"?>
<geometry>
<cell id="1" fill="6" region="1 -2 3 -4" />
<cell id="2" universe="5" fill="4" region="1 -2 3 -4" />
<cell id="101" universe="1" material="1" region="-5" />
<cell id="102" universe="1" material="2" region="5" />
<cell id="201" universe="2" material="1" region="-6" />
<cell id="202" universe="2" material="2" region="6" />
<cell id="301" universe="3" material="1" region="-7" />
<cell id="302" universe="3" material="2" region="7" />
<!-- 4 x 4 assembly -->
<lattice id="4">
<dimension>2 2</dimension>
<lower_left>-1.0 -1.0</lower_left>
<pitch>1.0 1.0</pitch>
<universes>
1 2
2 3
</universes>
</lattice>
<!-- 4 x 4 core -->
<lattice id="6">
<dimension>2 2</dimension>
<lower_left>-2.0 -2.0</lower_left>
<pitch>2.0 2.0</pitch>
<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>

17
examples/xml/lattice/nested/materials.xml Normal file
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<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="2">
<density value="1.0" units="g/cc" />
<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
<sab name="c_H_in_H2O" />
</material>
</materials>

10
examples/xml/lattice/nested/plots.xml Normal file
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<?xml version="1.0"?>
<plots>
<plot id="1" color_by="material">
<origin>0. 0. 0.</origin>
<width>4.0 4.0</width>
<pixels>400 400</pixels>
</plot>
</plots>

17
examples/xml/lattice/nested/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<!-- Parameters for k-eigenvalue calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>10000</particles>
<!-- Starting source -->
<source>
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
</settings>

20
examples/xml/lattice/nested/tallies.xml Normal file
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<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<dimension>4 4</dimension>
<lower_left>-2.0 -2.0</lower_left>
<width>1.0 1.0</width>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>

32
examples/xml/lattice/simple/geometry.xml Normal file
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<?xml version="1.0"?>
<geometry>
<cell id="1" fill="5" region="1 -2 3 -4" />
<cell id="101" universe="1" material="1" region="-5" />
<cell id="102" universe="1" material="2" region="5" />
<cell id="201" universe="2" material="1" region="-6" />
<cell id="202" universe="2" material="2" region="6" />
<cell id="301" universe="3" material="1" region="-7" />
<cell id="302" universe="3" material="2" region="7" />
<lattice id="5">
<dimension>4 4</dimension>
<lower_left>-2.0 -2.0</lower_left>
<pitch>1.0 1.0</pitch>
<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>

17
examples/xml/lattice/simple/materials.xml Normal file
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<?xml version="1.0"?>
<materials>
<!-- Definition of materials -->
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
<material id="2">
<density value="1.0" units="g/cc" />
<nuclide name="H1" ao="2.0" />
<nuclide name="O16" ao="1.0" />
<sab name="c_H_in_H2O" />
</material>
</materials>

10
examples/xml/lattice/simple/plots.xml Normal file
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<?xml version="1.0"?>
<plots>
<plot id="1" color_by="material">
<origin>0. 0. 0.</origin>
<width>4.0 4.0</width>
<pixels>400 400</pixels>
</plot>
</plots>

17
examples/xml/lattice/simple/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<!-- Parameters for k-eigenvalue calculation -->
<run_mode>eigenvalue</run_mode>
<batches>20</batches>
<inactive>10</inactive>
<particles>10000</particles>
<!-- Starting source -->
<source>
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
</settings>

20
examples/xml/lattice/simple/tallies.xml Normal file
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<?xml version="1.0"?>
<tallies>
<mesh id="1">
<type>regular</type>
<dimension>4 4</dimension>
<lower_left>-2.0 -2.0</lower_left>
<width>1.0 1.0</width>
</mesh>
<filter id="1" type="mesh">
<bins>1</bins>
</filter>
<tally id="1">
<filters>1</filters>
<scores>total</scores>
</tally>
</tallies>

27
examples/xml/pincell/geometry.xml Normal file
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<?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" region=" -1" /> <!-- UO2 Fuel -->
<cell id="2" material="2" region="1 -2" /> <!-- Helium gap -->
<cell id="3" material="3" region="2 -3" /> <!-- Zircaloy cladding -->
<cell id="4" material="4" region="3 4 -5 6 -7" /> <!-- Borated water -->
</geometry>

67
examples/xml/pincell/materials.xml Normal file
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<?xml version="1.0"?>
<materials>
<!--
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="U234" ao="4.4843e-06" />
<nuclide name="U235" ao="5.5815e-04" />
<nuclide name="U238" ao="2.2408e-02" />
<nuclide name="O16" ao="4.5829e-02" />
<nuclide name="O17" ao="1.1164e-04" />
</material>
<!-- Helium for gap -->
<material id="2">
<density value="0.001598" units="g/cm3" />
<nuclide name="He4" ao="2.4044e-04" />
</material>
<!-- Zircaloy 4 -->
<material id="3">
<density value="6.55" units="g/cm3" />
<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>
<!-- Borated water at 975 ppm -->
<material id="4">
<density value="0.740582" units="g/cm3" />
<nuclide name="B10" ao="8.0042e-06" />
<nuclide name="B11" ao="3.2218e-05" />
<nuclide name="H1" ao="4.9457e-02" />
<nuclide name="H2" ao="7.4196e-06" />
<nuclide name="O16" ao="2.4672e-02" />
<nuclide name="O17" ao="6.0099e-05" />
<sab name="c_H_in_H2O" />
</material>
</materials>

32
examples/xml/pincell/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<!-- Define how many particles to run and for how many batches -->
<run_mode>eigenvalue</run_mode>
<batches>100</batches>
<inactive>10</inactive>
<particles>1000</particles>
<!-- 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. -->
<mesh id="1">
<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>
</mesh>
<entropy_mesh>1</entropy_mesh>
</settings>

23
examples/xml/pincell/tallies.xml Normal file
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<?xml version="1.0"?>
<tallies>
<mesh id="2" type="regular">
<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>
<filter id="1" type="mesh">
<bins>2</bins>
</filter>
<filter id="2" type="energy">
<bins>0. 4. 20.0e6</bins>
</filter>
<tally id="1">
<filters>1 2</filters>
<scores>flux fission nu-fission</scores>
</tally>
</tallies>

10
examples/xml/pincell_multigroup/geometry.xml Normal file
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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell 1" region="-1" universe="0" />
<cell id="2" material="2" name="cell 2" region="1 4 -5 6 -7" universe="0" />
<surface coeffs="0 0 0.54" id="1" name="Fuel OR" type="z-cylinder" />
<surface boundary="reflective" coeffs="-0.63" id="4" name="left" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="5" name="right" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="6" name="bottom" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="7" name="top" type="y-plane" />
</geometry>

12
examples/xml/pincell_multigroup/materials.xml Normal file
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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>./mgxs.h5</cross_sections>
<material id="1" name="UO2 fuel">
<density units="macro" value="1.0" />
<macroscopic name="UO2" />
</material>
<material id="2" name="Water">
<density units="macro" value="1.0" />
<macroscopic name="LWTR" />
</material>
</materials>

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examples/xml/pincell_multigroup/mgxs.h5 Normal file
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examples/xml/pincell_multigroup/plots.xml Normal file
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<?xml version="1.0"?>
<plots>
<plot>
<id>1</id>
<filename>mat</filename>
<color_by>material</color_by>
<origin>0 0 0</origin>
<width>1.26 1.26</width>
<type>slice</type>
<pixels>1000 1000 </pixels>
<color id="1" rgb="255 0 0" />
<color id="2" rgb="0 0 0" />
<color id="3" rgb="0 255 0" />
<color id="4" rgb="0 0 255" />
</plot>
<plot>
<id>2</id>
<filename>cell</filename>
<color_by>cell</color_by>
<origin>0 0 0</origin>
<width>1.26 1.26</width>
<type>slice</type>
<pixels>1000 1000 </pixels>
</plot>
</plots>

13
examples/xml/pincell_multigroup/settings.xml Normal file
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<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>1000</particles>
<batches>100</batches>
<inactive>10</inactive>
<source strength="1.0">
<space type="box">
<parameters>-0.63 -0.63 -1 0.63 0.63 1</parameters>
</space>
</source>
<energy_mode>multi-group</energy_mode>
</settings>

18
examples/xml/pincell_multigroup/tallies.xml Normal file
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<?xml version='1.0' encoding='utf-8'?>
<tallies>
<mesh id="1" type="regular">
<dimension>100 100 1</dimension>
<lower_left>-0.63 -0.63 -1e+50</lower_left>
<upper_right>0.63 0.63 1e+50</upper_right>
</mesh>
<filter id="1" type="energy">
<bins>1e-05 0.0635 10.0 100.0 1000.0 500000.0 1000000.0 20000000.0</bins>
</filter>
<filter id="2" type="mesh">
<bins>1</bins>
</filter>
<tally id="1" name="tally 1">
<filters>1 2</filters>
<scores>flux fission nu-fission</scores>
</tally>
</tallies>

19
examples/xml/reflective/geometry.xml Normal file
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<?xml version="1.0"?>
<geometry>
<!-- Definition of Cells -->
<cell id="1">
<universe>0</universe>
<material>1</material>
<region>1 -2 3 -4 5 -6</region>
</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>

9
examples/xml/reflective/materials.xml Normal file
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@ -0,0 +1,9 @@
<?xml version="1.0"?>
<materials>
<material id="1">
<density value="4.5" units="g/cc" />
<nuclide name="U235" ao="1.0" />
</material>
</materials>

17
examples/xml/reflective/settings.xml Normal file
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<?xml version="1.0"?>
<settings>
<!-- Parameters for k-eigenvalue calculation -->
<run_mode>eigenvalue</run_mode>
<batches>500</batches>
<inactive>10</inactive>
<particles>10000</particles>
<!-- Starting source -->
<source>
<space type="box">
<parameters>-1 -1 -1 1 1 1</parameters>
</space>
</source>
</settings>