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Corrected tally slicing for Python API MultiGroupXS

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This commit is contained in:
Will Boyd 2015-10-03 11:40:52 -04:00
parent d58e902784
commit 54145a1be0
6 changed files with 0 additions and 84 deletions
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8
docs/source/pythonapi/examples/geometry.xml
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<?xml version='1.0' encoding='utf-8'?>
<geometry>
<cell id="1" material="10000" name="cell" surfaces="10000 -10001 10002 -10003" universe="0" />
<surface boundary="reflective" coeffs="-0.63" id="10000" type="x-plane" />
<surface boundary="reflective" coeffs="0.63" id="10001" type="x-plane" />
<surface boundary="reflective" coeffs="-0.63" id="10002" type="y-plane" />
<surface boundary="reflective" coeffs="0.63" id="10003" type="y-plane" />
</geometry>

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docs/source/pythonapi/examples/materials-xy.png
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12
docs/source/pythonapi/examples/materials.xml
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<?xml version='1.0' encoding='utf-8'?>
<materials>
<default_xs>71c</default_xs>
<material id="10000" name="moderator">
<density units="g/cc" value="5.0" />
<nuclide ao="0.006886019" name="U-238" />
<nuclide ao="0.01450188" name="O-16" />
<nuclide ao="0.002116053" name="Zr-90" />
<nuclide ao="0.028999667" name="H-1" />
<nuclide ao="0.000114142" name="U-235" />
</material>
</materials>

8
docs/source/pythonapi/examples/plots.xml
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<?xml version='1.0' encoding='utf-8'?>
<plots>
<plot basis="xy" color="mat" filename="materials-xy" id="1" type="slice">
<origin>0 0 0</origin>
<width>21.5 21.5</width>
<pixels>250 250</pixels>
</plot>
</plots>

17
docs/source/pythonapi/examples/settings.xml
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<?xml version='1.0' encoding='utf-8'?>
<settings>
<eigenvalue>
<particles>2500</particles>
<batches>50</batches>
<inactive>10</inactive>
</eigenvalue>
<source>
<space type="box">
<parameters>-0.63 -0.63 -0.63 0.63 0.63 0.63</parameters>
</space>
</source>
<output>
<tallies>true</tallies>
<summary>true</summary>
</output>
</settings>

39
docs/source/pythonapi/examples/tallies.xml
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<?xml version='1.0' encoding='utf-8'?>
<tallies>
<tally id="10014">
<filter bins="1" type="cell" />
<filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
<nuclides>total</nuclides>
<scores>scatter-P1 nu-fission</scores>
<estimator>analog</estimator>
</tally>
<tally id="10013">
<filter bins="1" type="cell" />
<filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux total</scores>
<estimator>analog</estimator>
</tally>
<tally id="10011">
<filter bins="1" type="cell" />
<filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
<nuclides>total</nuclides>
<scores>flux nu-fission</scores>
<estimator>tracklength</estimator>
</tally>
<tally id="10006">
<filter bins="1" type="cell" />
<filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energy" />
<filter bins="0.0 5.8e-08 1.4e-07 2.8e-07 6.25e-07 4e-06 0.00553 0.821 20.0" type="energyout" />
<nuclides>total</nuclides>
<scores>nu-scatter</scores>
<estimator>analog</estimator>
</tally>
<tally id="10008">
<filter bins="1" type="cell" />
<filter bins="0.0 20.0" type="energy" />
<nuclides>total</nuclides>
<scores>nu-fission</scores>
<estimator>analog</estimator>
</tally>
</tallies>