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Merge remote-tracking branch 'upstream/develop' into diff_tally6

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Sterling Harper 2016-11-03 17:01:15 -04:00
commit 902286a674
105 changed files with 1833 additions and 1868 deletions
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docs/source/usersguide/input.rst
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@ -1520,7 +1520,7 @@ The ``<tally>`` element accepts the following sub-elements:
.. code-block:: xml
<filter type="energy" bins="0.0 1.0 20.0" />
<filter type="energy" bins="0.0 1.0e6 20.0e6" />
then two energy bins will be created, one with energies between 0 and
1 MeV and the other with energies between 1 and 20 MeV.
@ -1535,7 +1535,7 @@ The ``<tally>`` element accepts the following sub-elements:
.. code-block:: xml
<filter type="energyout" bins="0.0 1.0 20.0" />
<filter type="energyout" bins="0.0 1.0e6 20.0e6" />
then two post-collision energy bins will be created, one with
energies between 0 and 1 MeV and the other with energies between
@ -1854,7 +1854,7 @@ The ``<tally>`` element accepts the following sub-elements:
| |particles. The neutrino energy does not contribute |
| |to this response. The prompt and delayed |
| |:math:`\gamma`-rays are assumed to deposit their |
| |energy locally. Units are MeV per source particle. |
| |energy locally. Units are eV per source particle. |
+----------------------+---------------------------------------------------+
|fission-q-prompt |The prompt fission energy production rate. This |
| |energy comes in the form of fission fragment |
@ -1863,7 +1863,7 @@ The ``<tally>`` element accepts the following sub-elements:
| |incident energy and it requires that the nuclear |
| |data library contains the optional fission energy |
| |release data. Energy is assumed to be deposited |
| |locally. Units are MeV per source particle. |
| |locally. Units are eV per source particle. |
+----------------------+---------------------------------------------------+
|fission-q-recoverable |The recoverable fission energy production rate. |
| |This energy comes in the form of fission fragment |
@ -1874,7 +1874,7 @@ The ``<tally>`` element accepts the following sub-elements:
| |incident neutron energy and it requires that the |
| |nuclear data library contains the optional fission |
| |energy release data. Energy is assumed to be |
| |deposited locally. Units are MeV per source |
| |deposited locally. Units are eV per source |
| |paticle. |
+----------------------+---------------------------------------------------+
|decay-rate |The delayed-nu-fission-weighted decay rate where |
@ -2296,7 +2296,7 @@ attributes/sub-elements:
The width of mesh cells in each direction.
:energy:
Energy bins [in MeV], listed in ascending order (e.g. 0.0 0.625e-7 20.0)
Energy bins [in eV], listed in ascending order (e.g. 0.0 0.625 20.0e6)
for CMFD tallies and acceleration. If no energy bins are listed, OpenMC
automatically assumes a one energy group calculation over the entire
energy range.