Updated docstring to better explain chain_file and micro_xs

This commit is contained in:
Paul Romano 2022-11-21 15:20:12 -06:00
parent d6a4a3ecb9
commit ea0892f0f3

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@ -31,6 +31,9 @@ class IndependentOperator(OpenMCOperator):
passed to an integrator class, such as
:class:`openmc.deplete.CECMIntegrator`.
Note that passing an empty :class:`~openmc.deplete.MicroXS` instance to the
``micro_xs`` argument allows a decay-only calculation to be run.
.. versionadded:: 0.13.1
Parameters
@ -38,9 +41,11 @@ class IndependentOperator(OpenMCOperator):
materials : openmc.Materials
Materials to deplete.
micro_xs : MicroXS
One-group microscopic cross sections in [b] .
One-group microscopic cross sections in [b]. If the
:class:`~openmc.deplete.MicroXS` is empty, a decay-only calculation will
be run.
chain_file : str
Path to the depletion chain XML file. Defaults to
Path to the depletion chain XML file. Defaults to
``openmc.config['chain_file']``.
keff : 2-tuple of float, optional
keff eigenvalue and uncertainty from transport calculation.
@ -169,9 +174,12 @@ class IndependentOperator(OpenMCOperator):
Dictionary with nuclide names as keys and nuclide concentrations as
values.
micro_xs : MicroXS
One-group microscopic cross sections.
One-group microscopic cross sections in [b]. If the
:class:`~openmc.deplete.MicroXS` is empty, a decay-only calculation
will be run.
chain_file : str, optional
Path to the depletion chain XML file.
Path to the depletion chain XML file. Defaults to
``openmc.config['chain_file']``.
nuc_units : {'atom/cm3', 'atom/b-cm'}, optional
Units for nuclide concentration.
keff : 2-tuple of float, optional