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Added paragraph on new scattering subelement for nuclides

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Will Boyd 2015-04-27 00:39:02 -04:00
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docs/source/usersguide/input.rst
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@ -1015,6 +1015,15 @@ 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 "ace" to use the scattering laws specified in the
ACE files (default). Alternatively, when set to "lab", the ACE 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: