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Updated documentation for batches and energy_grid.

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Paul Romano 2012-03-19 10:43:27 -04:00
parent 47364fae97
commit ad53071fc4
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docs/source/usersguide/input.rst
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@ -307,16 +307,23 @@ settings.xml file.
The ``criticality`` element indicates that a criticality calculation should be
performed. It has the following attributes/sub-elements:
:cycles:
The number of total fission source iterations.
:batches:
The total number of batches, where each batch corresponds to multiple
fission source iterations. Batching is done to eliminate correlation between
realizations of random variables.
*Default*: None
:generations_per_batch:
The number of total fission source iterations per batch.
*Default*: 1
:inactive:
The number of inactive fission source iterations. In general, the starting
cycles in a criticality calculation can not be used to contribute to tallies
since the fission source distribution and eigenvalue are generally not
converged immediately
The number of inactive batches. In general, the starting cycles in a
criticality calculation can not be used to contribute to tallies since the
fission source distribution and eigenvalue are generally not converged
immediately.
*Default*: None
@ -353,6 +360,18 @@ default. This element has the following attributes/sub-elements:
*Default*: 1.0
``energy_grid`` Element
-----------------------
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.
*Default*: union
``entropy`` Element
-------------------