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Added python API support for the new options; dont yet have a capability to build the mgxs xml file. Also wrote (and check as needed) the run_CE flag to the summary file and state points.

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Adam Nelson 2015-11-14 13:33:05 -05:00
parent 85a4c3f272
commit baad6cf274
7 changed files with 288 additions and 23 deletions
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docs/source/usersguide/input.rst
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@ -1151,14 +1151,17 @@ Each ``material`` element can have the following attributes or sub-elements:
The "sum" unit indicates that the density should be calculated as the sum
of the atom fractions for each nuclide in the material. This should not be
used in conjunction with weight percents. The "macro" unit is used with
a ``macroscopic`` to indicate that the density is already included in the
library and thus not needed here. However, if a value is provided for the
``value``, then this is treated as a number density multiplier on the
macroscopic cross sections in the multi-group data. This can be used,
a ``macroscopic`` quantity to indicate that the density is already included
in the library and thus not needed here. However, if a value is provided
for the ``value``, then this is treated as a number density multiplier on
the macroscopic cross sections in the multi-group data. This can be used,
for example, when perturbing the density slightly.
*Default*: None
.. note:: A ``macroscopic`` quantity can not be used in conjunction with a
``nuclide``, ``element``, or ``sab`` quantity.
:nuclide:
An element with attributes/sub-elements called ``name``, ``xs``, and ``ao``
or ``wo``. The ``name`` attribute is the name of the cross-section for a