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Updating per the latest round of comments. This includes simplifying the notebook significantly, and adding a get_xsdata method to Library.

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Adam Nelson 2016-05-13 22:32:48 -04:00
parent e9fc744ba5
commit eb20de6a51
6 changed files with 393 additions and 1551 deletions
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6
docs/source/usersguide/mgxs_library.rst
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@ -8,10 +8,10 @@ OpenMC can be run in continuous-energy mode or multi-group mode, provided the
nuclear data is available. In continuous-energy mode, the
``cross_sections.xml`` file contains necessary meta-data for each data set,
including the name and a file system location where the complete library
can be found. In multi-group mode, this ``cross_sections.xml`` file contains
can be found. In multi-group mode, this ``mgxs.xml`` file contains
this same meta-data describing the nuclide or material, but also contains the
group-wise nuclear data. This portion of the manual describes the format of
the multi-group data library required to be used in the ``cross_sections.xml``
the multi-group data library required to be used in the ``mgxs.xml``
file.
Similar to the other input file types, the multi-group library is provided in
@ -23,7 +23,7 @@ materials.
.. _XML: http://www.w3.org/XML/
------------------------------------------------
MGXS Library Specification -- cross_sections.xml
MGXS Library Specification -- mgxs.xml
------------------------------------------------
The multi-group library meta-data is contained within the groups_,