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Updated docstring to better explain chain_file and micro_xs
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1 changed files with 12 additions and 4 deletions
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@ -31,6 +31,9 @@ class IndependentOperator(OpenMCOperator):
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passed to an integrator class, such as
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:class:`openmc.deplete.CECMIntegrator`.
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Note that passing an empty :class:`~openmc.deplete.MicroXS` instance to the
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``micro_xs`` argument allows a decay-only calculation to be run.
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.. versionadded:: 0.13.1
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Parameters
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@ -38,9 +41,11 @@ class IndependentOperator(OpenMCOperator):
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materials : openmc.Materials
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Materials to deplete.
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micro_xs : MicroXS
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One-group microscopic cross sections in [b] .
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One-group microscopic cross sections in [b]. If the
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:class:`~openmc.deplete.MicroXS` is empty, a decay-only calculation will
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be run.
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chain_file : str
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Path to the depletion chain XML file. Defaults to
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Path to the depletion chain XML file. Defaults to
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``openmc.config['chain_file']``.
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keff : 2-tuple of float, optional
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keff eigenvalue and uncertainty from transport calculation.
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@ -169,9 +174,12 @@ class IndependentOperator(OpenMCOperator):
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Dictionary with nuclide names as keys and nuclide concentrations as
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values.
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micro_xs : MicroXS
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One-group microscopic cross sections.
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One-group microscopic cross sections in [b]. If the
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:class:`~openmc.deplete.MicroXS` is empty, a decay-only calculation
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will be run.
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chain_file : str, optional
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Path to the depletion chain XML file.
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Path to the depletion chain XML file. Defaults to
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``openmc.config['chain_file']``.
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nuc_units : {'atom/cm3', 'atom/b-cm'}, optional
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Units for nuclide concentration.
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keff : 2-tuple of float, optional
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