crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-28 06:05:58 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions 5

Merge pull request #201 from mit-crpg/xml

Browse source 
New XML interface and Library
This commit is contained in:
Paul Romano 2013-11-29 09:13:29 -08:00
commit 0309a67815
91 changed files with 41025 additions and 4557 deletions
Download patch file Download diff file Expand all files Collapse all files

25
docs/source/usersguide/input.rst
View file

@ -198,19 +198,26 @@ tally data, this option can significantly improve the parallel efficiency.
--------------------
The ``<output>`` element determines what output files should be written to disk
during the run. This element has no attributes or sub-elements and should be set
to a list of strings separated by spaces. Valid options are "summary",
"cross-sections", and "tallies". For example, if you want the summary and cross
sections summary file to be written, this element should be given as:
during the run. The sub-elements are described below, where "true" will write
out the file and "false" will not.
.. code-block:: xml
:cross_sections:
Writes out an ASCII summary file of the cross sections that were read in.
<output>summary cross_sections</output>
*Default*: false
.. note:: The tally results will be written to a binary/HDF5 state point file by
default.
:summary:
Writes out an ASCII summary file describing all of the user input files that
were read in.
*Default*: "tallies"
*Default*: false
:tallies:
Write out an ASCII file of tally results.
*Default*: true
.. note:: The tally results will always be written to a binary/HDF5 state point file.
``<output_path>`` Element
-------------------------