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

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Sterling Harper 2015-01-08 19:05:24 -05:00
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docs/source/usersguide/input.rst
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@ -134,13 +134,15 @@ should be performed. It has the following attributes/sub-elements:
-------------------------
The ``<energy_grid>`` element determines the treatment of the energy grid during
a simulation. Setting this element to "nuclide" will cause OpenMC to use a
nuclide's energy grid when determining what points to interpolate between for
determining cross sections (i.e. non-unionized energy grid). To use a unionized
energy grid, set this element to "union". Note that the unionized energy grid
treatment is slightly different than that employed in Serpent.
a simulation. The valid options are "nuclide" and "logarithm". Setting this
element to "nuclide" will cause OpenMC to use a nuclide's energy grid when
determining what points to interpolate between for determining cross sections
(i.e. non-unionized energy grid). Setting this element to "logarithm" causes
OpenMC to use a logarithmic mapping technique described in LA-UR-14-24530_.
*Default*: union
*Default*: logarithm
.. _LA-UR-14-24530: https://laws.lanl.gov/vhosts/mcnp.lanl.gov/pdf_files/la-ur-14-24530.pdf
``<entropy>`` Element
---------------------
@ -182,6 +184,16 @@ performed. It has the following attributes/sub-elements:
*Default*: None
``<log_grid_bins>`` Element
---------------------------
The ``<log_grid_bins>`` element indicates the number of bins to use for the
logarithmic-mapped energy grid. Using more bins will result in energy grid
searches over a smaller range at the expense of more memory. The default is
based on the recommended value in LA-UR-14-24530_.
*Default*: 8000
.. _natural_elements:
``<natural_elements>`` Element
@ -1097,6 +1109,16 @@ The ``<tally>`` element accepts the following sub-elements:
*Default*: total
:estimator:
The estimator element is used to force the use of either ``analog`` or
``tracklength`` tally estimation. ''analog'' is generally less efficient
though it can be used with every score type. ''tracklength'' is generally
the most efficient, though its usage is restricted to tallies that do not
score particle information which requires a collision to have occured, such
as a scattering tally which utilizes outgoing energy filters.
*Default*: ``tracklength`` but will revert to analog if necessary.
:scores:
A space-separated list of the desired responses to be accumulated. Accepted
options are "flux", "total", "scatter", "absorption", "fission",
@ -1647,3 +1669,15 @@ into MATLAB using PETSc-MATLAB utilities. This option can be
turned on with "true" and off with "false".
*Default*: false
------------------------------------
ERSN-OpenMC Graphical User Interface
------------------------------------
A third-party Java-based user-friendly graphical user interface for creating XML
input files called ERSN-OpenMC_ is developed and maintained by members of the
Radiation and Nuclear Systems Group at the Faculty of Sciences Tetouan, Morocco.
The GUI also allows one to automatically download prerequisites for installing and
running OpenMC.
.. _ERSN-OpenMC: https://github.com/EL-Bakkali-Jaafar/ERSN-OpenMC