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Merged iso-in-lab

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Adam Nelson 2015-11-10 05:32:52 -05:00
commit f7ffa71e4f
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docs/source/usersguide/input.rst
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@ -1175,6 +1175,15 @@ Each ``material`` element can have the following attributes or sub-elements:
.. note:: If one nuclide is specified in atom percent, all others must also
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 "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
transport codes and to quantify the effects of anisotropic scattering.
*Default*: None
:element:
@ -1201,6 +1210,16 @@ 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 "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
transport codes and to quantify the effects of anisotropic scattering.
*Default*: None
:sab:
Associates an S(a,b) table with the material. This element has