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Include fissionable material in fixed source test
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0e0984a5ff
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2 changed files with 5 additions and 4 deletions
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@ -4,6 +4,7 @@
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<material id="1">
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<density value="7.5" units="g/cc" />
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<nuclide name="O-16" xs="71c" ao="1.0" />
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<nuclide name="U-238" xs="71c" ao="0.0001" />
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</material>
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</materials>
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@ -1,6 +1,6 @@
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tally 1:
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4.538791E+02
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2.073271E+04
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4.563929E+02
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2.091711E+04
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leakage:
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9.830000E+00
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9.663900E+00
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9.780000E+00
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9.566400E+00
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