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Add note about specifying volume for depletion

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Paul Romano 2021-03-08 09:20:51 -06:00
parent b66664cbf6
commit 4f9bbca7f3
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docs/source/usersguide/depletion.rst
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@ -30,6 +30,12 @@ operator class requires a :class:`openmc.Geometry` instance and a
Any material that contains a fissionable nuclide is depleted by default, but
this can behavior can be changed with the :attr:`Material.depletable` attribute.
.. important:: The volume must be specified for each material that is depleted by
setting the :attr:`Material.volume` attribute. This is necessary
in order to calculate the proper normalization of tally results
based on the source rate.
:mod:`openmc.deplete` supports multiple time-integration methods for determining
material compositions over time. Each method appears as a different class.
For example, :class:`openmc.deplete.CECMIntegrator` runs a depletion calculation