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Now using a "data" descriptor rather than "ace" for the nuclide/element scattering XML tag

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Will Boyd 2015-11-09 09:26:48 -05:00
parent 4db72c90af
commit baa0b4c10c
5 changed files with 19 additions and 19 deletions
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12
docs/source/usersguide/input.rst
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@ -1137,9 +1137,9 @@ Each ``material`` element can have the following attributes or sub-elements:
be given in atom percent. The same applies for weight percentages.
An optional attribute/sub-element for each nuclide is ``scattering``. This
attribute may be set to "ace" to use the scattering laws specified in the
ACE files (default). Alternatively, when set to "iso-in-lab", the ACE
scattering laws are used to sample the outgoing energy but an
attribute may be set to "data" to use the scattering laws specified by the
cross section library (default). Alternatively, when set to "iso-in-lab",
the scattering laws are used to sample the outgoing energy but an
isotropic-in-lab distribution is used to sample the outgoing angle at each
scattering interaction. The ``scattering`` attribute may be most useful
when using OpenMC to compute multi-group cross-sections for deterministic
@ -1172,9 +1172,9 @@ Each ``material`` element can have the following attributes or sub-elements:
*Default*: None
An optional attribute/sub-element for each element is ``scattering``. This
attribute may be set to "ace" to use the scattering laws specified in the
ACE files (default). Alternatively, when set to "iso-in-lab", the ACE
scattering laws are used to sample the outgoing energy but an
attribute may be set to "data" to use the scattering laws specified by the
cross section library (default). Alternatively, when set to "iso-in-lab",
the scattering laws are used to sample the outgoing energy but an
isotropic-in-lab distribution is used to sample the outgoing angle at each
scattering interaction. The ``scattering`` attribute may be most useful
when using OpenMC to compute multi-group cross-sections for deterministic