add a test case dirs and files

test case
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dryuri92 2020-03-15 19:43:18 +03:00 committed by GitHub
parent c3fff76bea
commit f9e8eda4c4
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40 changed files with 390 additions and 0 deletions

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell" region="33 -34 35 -36" temperature="520.0" universe="9" />
<surface boundary="reflective" coeffs="-11.1" id="33" type="x-plane" />
<surface boundary="reflective" coeffs="11.1" id="34" type="x-plane" />
<surface boundary="reflective" coeffs="-11.1" id="35" type="y-plane" />
<surface boundary="reflective" coeffs="11.1" id="36" type="y-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../../../macro_2g.h5</cross_sections>
<material id="1" name="test material">
<density units="sum" />
<nuclide ao="1" name="macro" />
</material>
</materials>

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k-combined:
1.422739E+00 1.661420E-03
k-analytical:
1.418514E+00

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<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>5000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-11.1 -11.1 -11.1 11.1 11.1 11.1</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<temperature_method>interpolation</temperature_method>
</settings>

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell" region="37 -38 39 -40" temperature="600" universe="10" />
<surface boundary="reflective" coeffs="-11.1" id="37" type="x-plane" />
<surface boundary="reflective" coeffs="11.1" id="38" type="x-plane" />
<surface boundary="reflective" coeffs="-11.1" id="39" type="y-plane" />
<surface boundary="reflective" coeffs="11.1" id="40" type="y-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../../../macro_2g.h5</cross_sections>
<material id="1" name="test material">
<density units="sum" />
<nuclide ao="1" name="macro" />
</material>
</materials>

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k-combined:
1.410995E+00 2.169214E-03
k-analytical:
1.410164E+00

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<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>5000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-11.1 -11.1 -11.1 11.1 11.1 11.1</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<temperature_method>interpolation</temperature_method>
</settings>

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell" region="21 -22 23 -24" temperature="300.0" universe="6" />
<surface boundary="reflective" coeffs="-11.1" id="21" type="x-plane" />
<surface boundary="reflective" coeffs="11.1" id="22" type="x-plane" />
<surface boundary="reflective" coeffs="-11.1" id="23" type="y-plane" />
<surface boundary="reflective" coeffs="11.1" id="24" type="y-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../../../macro_2g.h5</cross_sections>
<material id="1" name="test material">
<density units="sum" />
<nuclide ao="1" name="macro" />
</material>
</materials>

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k-combined:
1.443970E+00 3.267499E-03
k-analytical:
1.440410E+00

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<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>5000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-11.1 -11.1 -11.1 11.1 11.1 11.1</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<temperature_method>nearest</temperature_method>
</settings>

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell" region="25 -26 27 -28" temperature="600.0" universe="7" />
<surface boundary="reflective" coeffs="-11.1" id="25" type="x-plane" />
<surface boundary="reflective" coeffs="11.1" id="26" type="x-plane" />
<surface boundary="reflective" coeffs="-11.1" id="27" type="y-plane" />
<surface boundary="reflective" coeffs="11.1" id="28" type="y-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../../../macro_2g.h5</cross_sections>
<material id="1" name="test material">
<density units="sum" />
<nuclide ao="1" name="macro" />
</material>
</materials>

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k-combined:
1.410995E+00 2.169214E-03
k-analytical:
1.410164E+00

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<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>5000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-11.1 -11.1 -11.1 11.1 11.1 11.1</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<temperature_method>nearest</temperature_method>
</settings>

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell" region="29 -30 31 -32" temperature="900.0" universe="8" />
<surface boundary="reflective" coeffs="-11.1" id="29" type="x-plane" />
<surface boundary="reflective" coeffs="11.1" id="30" type="x-plane" />
<surface boundary="reflective" coeffs="-11.1" id="31" type="y-plane" />
<surface boundary="reflective" coeffs="11.1" id="32" type="y-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../../../macro_2g.h5</cross_sections>
<material id="1" name="test material">
<density units="sum" />
<nuclide ao="1" name="macro" />
</material>
</materials>

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k-combined:
1.411726E+00 2.151179E-03
k-analytical:
1.407830E+00

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<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>5000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-11.1 -11.1 -11.1 11.1 11.1 11.1</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<temperature_method>nearest</temperature_method>
</settings>

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell" region="13 -14 15 -16" temperature="520.0" universe="4" />
<surface boundary="reflective" coeffs="-11.1" id="13" type="x-plane" />
<surface boundary="reflective" coeffs="11.1" id="14" type="x-plane" />
<surface boundary="reflective" coeffs="-11.1" id="15" type="y-plane" />
<surface boundary="reflective" coeffs="11.1" id="16" type="y-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../../../micro_2g.h5</cross_sections>
<material depletable="true" id="1" name="test material">
<density units="sum" />
<nuclide ao="1" name="H" />
<nuclide ao="1" name="O" />
<nuclide ao="1" name="Zr" />
<nuclide ao="1" name="U235" />
<nuclide ao="1" name="U238" />
</material>
</materials>

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@ -0,0 +1,4 @@
k-combined:
1.422739E+00 1.661420E-03
k-analytical:
1.418514E+00

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@ -0,0 +1,17 @@
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>5000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-11.1 -11.1 -11.1 11.1 11.1 11.1</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<temperature_method>interpolation</temperature_method>
</settings>

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell" region="17 -18 19 -20" temperature="600.0" universe="5" />
<surface boundary="reflective" coeffs="-11.1" id="17" type="x-plane" />
<surface boundary="reflective" coeffs="11.1" id="18" type="x-plane" />
<surface boundary="reflective" coeffs="-11.1" id="19" type="y-plane" />
<surface boundary="reflective" coeffs="11.1" id="20" type="y-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../../../micro_2g.h5</cross_sections>
<material depletable="true" id="1" name="test material">
<density units="sum" />
<nuclide ao="1" name="H" />
<nuclide ao="1" name="O" />
<nuclide ao="1" name="Zr" />
<nuclide ao="1" name="U235" />
<nuclide ao="1" name="U238" />
</material>
</materials>

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k-combined:
1.410995E+00 2.169214E-03
k-analytical:
1.410164E+00

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<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>5000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-11.1 -11.1 -11.1 11.1 11.1 11.1</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<temperature_method>interpolation</temperature_method>
</settings>

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell" region="1 -2 3 -4" temperature="300.0" universe="1" />
<surface boundary="reflective" coeffs="-11.1" id="1" type="x-plane" />
<surface boundary="reflective" coeffs="11.1" id="2" type="x-plane" />
<surface boundary="reflective" coeffs="-11.1" id="3" type="y-plane" />
<surface boundary="reflective" coeffs="11.1" id="4" type="y-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../../../micro_2g.h5</cross_sections>
<material depletable="true" id="1" name="test material">
<density units="sum" />
<nuclide ao="1" name="H" />
<nuclide ao="1" name="O" />
<nuclide ao="1" name="Zr" />
<nuclide ao="1" name="U235" />
<nuclide ao="1" name="U238" />
</material>
</materials>

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k-combined:
1.443970E+00 3.267499E-03
k-analytical:
1.440410E+00

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@ -0,0 +1,17 @@
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>5000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-11.1 -11.1 -11.1 11.1 11.1 11.1</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<temperature_method>nearest</temperature_method>
</settings>

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell" region="5 -6 7 -8" temperature="600.0" universe="2" />
<surface boundary="reflective" coeffs="-11.1" id="5" type="x-plane" />
<surface boundary="reflective" coeffs="11.1" id="6" type="x-plane" />
<surface boundary="reflective" coeffs="-11.1" id="7" type="y-plane" />
<surface boundary="reflective" coeffs="11.1" id="8" type="y-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../../../micro_2g.h5</cross_sections>
<material depletable="true" id="1" name="test material">
<density units="sum" />
<nuclide ao="1" name="H" />
<nuclide ao="1" name="O" />
<nuclide ao="1" name="Zr" />
<nuclide ao="1" name="U235" />
<nuclide ao="1" name="U238" />
</material>
</materials>

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k-combined:
1.410995E+00 2.169214E-03
k-analytical:
1.410164E+00

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@ -0,0 +1,17 @@
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>5000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-11.1 -11.1 -11.1 11.1 11.1 11.1</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<temperature_method>nearest</temperature_method>
</settings>

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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="1" name="cell" region="9 -10 11 -12" temperature="900.0" universe="3" />
<surface boundary="reflective" coeffs="-11.1" id="9" type="x-plane" />
<surface boundary="reflective" coeffs="11.1" id="10" type="x-plane" />
<surface boundary="reflective" coeffs="-11.1" id="11" type="y-plane" />
<surface boundary="reflective" coeffs="11.1" id="12" type="y-plane" />
</geometry>

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<?xml version='1.0' encoding='utf-8'?>
<materials>
<cross_sections>../../../micro_2g.h5</cross_sections>
<material depletable="true" id="1" name="test material">
<density units="sum" />
<nuclide ao="1" name="H" />
<nuclide ao="1" name="O" />
<nuclide ao="1" name="Zr" />
<nuclide ao="1" name="U235" />
<nuclide ao="1" name="U238" />
</material>
</materials>

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k-combined:
1.411726E+00 2.151179E-03
k-analytical:
1.407830E+00

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@ -0,0 +1,17 @@
<?xml version='1.0' encoding='utf-8'?>
<settings>
<run_mode>eigenvalue</run_mode>
<particles>5000</particles>
<batches>15</batches>
<inactive>5</inactive>
<source strength="1.0">
<space type="fission">
<parameters>-11.1 -11.1 -11.1 11.1 11.1 11.1</parameters>
</space>
</source>
<output>
<summary>false</summary>
</output>
<energy_mode>multi-group</energy_mode>
<temperature_method>nearest</temperature_method>
</settings>