From 4e808a4257bbb1d399d511307597168a4bb1b2f3 Mon Sep 17 00:00:00 2001 From: Will Boyd Date: Mon, 27 Apr 2015 00:39:02 -0400 Subject: [PATCH] Added paragraph on new scattering subelement for nuclides --- docs/source/usersguide/input.rst | 9 +++++++++ 1 file changed, 9 insertions(+) diff --git a/docs/source/usersguide/input.rst b/docs/source/usersguide/input.rst index d98804c86..c1231e9a8 100644 --- a/docs/source/usersguide/input.rst +++ b/docs/source/usersguide/input.rst @@ -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: