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Merging with upstream.

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Adam Nelson 2012-12-05 10:13:03 -05:00
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docs/source/usersguide/input.rst
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@ -69,37 +69,6 @@ deviation.
*Default*: off
``<criticality>`` Element
-------------------------
The ``<criticality>`` element indicates that a criticality calculation should be
performed. It has the following attributes/sub-elements:
: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 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
:particles:
The number of neutrons to simulate per fission source iteration.
*Default*: None
.. _cross_sections:
``<cross_sections>`` Element
@ -130,6 +99,37 @@ default. This element has the following attributes/sub-elements:
*Default*: 1.0
``<eigenvalue>`` Element
------------------------
The ``<eigenvalue>`` element indicates that a :math:`k`-eigenvalue calculation
should be performed. It has the following attributes/sub-elements:
: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 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
:particles:
The number of neutrons to simulate per fission source iteration.
*Default*: None
``<energy_grid>`` Element
-------------------------