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added treatment of delayed neutrons to the multi-group solver

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Sam Shaner 2016-10-13 14:38:06 -04:00
parent 9035f6951e
commit 89149ea7eb
15 changed files with 3019 additions and 805 deletions
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12
docs/source/io_formats/mgxs_library.rst
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@ -15,8 +15,9 @@ to be used in the ``mgxs.h5`` file.
The multi-group library is provided in the HDF5_ format. This library must
provide some meta-data about the library itself (such as the number of
groups and the group structure, etc.) as well as the actual cross section
data itself for each of the necessary nuclides or materials.
energy groups, delayed groups, and the energy group structure, etc.) as
well as the actual cross section data itself for each of the necessary
nuclides or materials.
.. _HDF5: http://www.hdfgroup.org/HDF5/
@ -28,7 +29,8 @@ MGXS Library Specification
**/**
:Attributes: - **groups** (*int*) -- Number of energy groups
:Attributes: - **energy_groups** (*int*) -- Number of energy groups
- **delayed_groups** (*int*) -- Number of delayed groups (optional)
- **group structure** (*double[]*) -- Monotonically increasing
list of group boundaries, in units of MeV. The length of this
array should be the number of groups plus 1.
@ -110,7 +112,7 @@ Temperature-dependent data, provided for temperature <TTT>K.
spectra as well and thus will have one additional dimension
for the outgoing energy group. In this case, `nu-fission` has the
same dimensionality as `multiplicity matrix`.
- **inverse velocities** (*double[]*) -- Average inverse velocity
- **inverse-velocity** (*double[]*) -- Average inverse velocity
for each of the groups in the library. This dataset is optional.
**/<library name>/<TTT>K/scatter data/**
@ -159,4 +161,4 @@ Data specific to neutron scattering for the temperature <TTT>K
The former is used when `representation` is "isotropic", and the
latter when `representation` is "angle". Finally, the g_out
dimension has a dimensionality of `g_out bounds`[0] to
`g_out bounds`[1].
`g_out bounds`[1].

12
docs/source/usersguide/input.rst
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@ -1681,8 +1681,6 @@ The ``<tally>`` element accepts the following sub-elements:
<filter type="delayedgroup" bins="1 2 3 4 5 6" />
.. note:: This filter type is not used in the multi-group :ref:`energy_mode`.
: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
@ -1863,12 +1861,10 @@ The ``<tally>`` element accepts the following sub-elements:
|Score | Description |
+======================+===================================================+
|delayed-nu-fission |Total production of delayed neutrons due to |
| |fission. This score type is not used in the |
| |multi-group :ref:`energy_mode`. |
| |fission. |
+----------------------+---------------------------------------------------+
|prompt-nu-fission |Total production of prompt neutrons due to |
| |fission. This score type is not used in the |
| |multi-group :ref:`energy_mode`. |
| |fission. |
+----------------------+---------------------------------------------------+
|nu-fission |Total production of neutrons due to fission. |
+----------------------+---------------------------------------------------+
@ -1897,8 +1893,6 @@ The ``<tally>`` element accepts the following sub-elements:
+----------------------+---------------------------------------------------+
|inverse-velocity |The flux-weighted inverse velocity where the |
| |velocity is in units of centimeters per second. |
| |This score type is not used in the |
| |multi-group :ref:`energy_mode`. |
+----------------------+---------------------------------------------------+
|kappa-fission |The recoverable energy production rate due to |
| |fission. The recoverable energy is defined as the |
@ -1934,8 +1928,6 @@ The ``<tally>`` element accepts the following sub-elements:
+----------------------+---------------------------------------------------+
|decay-rate |The delayed-nu-fission-weighted decay rate where |
| |the decay rate is in units of inverse seconds. |
| |This score type is not used in the |
| |multi-group :ref:`energy_mode`. |
+----------------------+---------------------------------------------------+
.. note::