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Document openmc.deplete.nuclide.FissionYield

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Andrew Johnson 2019-08-12 15:15:26 -05:00
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docs/source/pythonapi/deplete.rst
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@ -66,6 +66,7 @@ for a depletion chain:
Nuclide
ReactionTuple
FissionYieldDistribution
FissionYield
The following classes are used during a depletion simulation and store auxiliary
data, such as number densities and reaction rates for each material.