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Fixed merge conflict with develop

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Will Boyd 2015-10-26 00:11:37 -04:00
commit e230ad3c8a
31 changed files with 833 additions and 153 deletions
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docs/source/usersguide/input.rst
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@ -1233,8 +1233,8 @@ The ``<tally>`` element accepts the following sub-elements:
:type:
The type of the filter. Accepted options are "cell", "cellborn",
"material", "universe", "energy", "energyout", "mesh", and
"distribcell".
"material", "universe", "energy", "energyout", "mesh", "distribcell",
and "delayedgroup".
:bins:
For each filter type, the corresponding ``bins`` entry is given as
@ -1352,6 +1352,15 @@ The ``<tally>`` element accepts the following sub-elements:
not accept more than one cell ID. It is not recommended to combine
this filter with a cell or mesh filter.
:delayedgroup:
A list of delayed neutron precursor groups for which the tally should
be accumulated. For instance, to tally to all 6 delayed groups in the
ENDF/B-VII.1 library the filter is specified as:
.. code-block:: xml
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
:nuclides:
If specified, the scores listed will be for particular nuclides, not the
summation of reactions from all nuclides. The format for nuclides should be
@ -1381,10 +1390,10 @@ The ``<tally>`` element accepts the following sub-elements:
:scores:
A space-separated list of the desired responses to be accumulated. Accepted
options are "flux", "total", "scatter", "absorption", "fission",
"nu-fission", "kappa-fission", "nu-scatter", "scatter-N", "scatter-PN",
"scatter-YN", "nu-scatter-N", "nu-scatter-PN", "nu-scatter-YN", "flux-YN",
"total-YN", "current", and "events". These corresponding to the following
physical quantities:
"nu-fission", "delayed-nu-fission", "kappa-fission", "nu-scatter",
"scatter-N", "scatter-PN", "scatter-YN", "nu-scatter-N", "nu-scatter-PN",
"nu-scatter-YN", "flux-YN", "total-YN", "current", and "events". These
correspond to the following physical quantities:
:flux:
Total flux in particle-cm per source particle. Note: The ``analog``
@ -1409,6 +1418,10 @@ The ``<tally>`` element accepts the following sub-elements:
Total production of neutrons due to fission. Units are neutrons produced
per source neutron.
:delayed-nu-fission:
Total production of delayed neutrons due to fission. Units are neutrons produced
per source neutron.
:kappa-fission:
The recoverable energy production rate due to fission. The recoverable
energy is defined as the fission product kinetic energy, prompt and