crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-26 21:25:36 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions

Added instructions on using JEFF ACE data from NEA.

Browse source
This commit is contained in:
Paul Romano 2013-01-09 16:11:22 -05:00
parent 7720f33327
commit 5e4509fa53
1 changed files with 48 additions and 11 deletions
Download patch file Download diff file Expand all files Collapse all files

59
docs/source/usersguide/install.rst
View file

@ -142,26 +142,63 @@ This will build an executable named ``openmc``.
.. _Cygwin: http://www.cygwin.com/
---------------------------
Cross-Section Configuration
Cross Section Configuration
---------------------------
In order to run a simulation with OpenMC, you will need cross-section data for
each nuclide in your problem. Since OpenMC uses ACE format cross-sections, you
can use nuclear data distributed with MCNP_ or Serpent_.
In order to run a simulation with OpenMC, you will need cross section data for
each nuclide in your problem. Since OpenMC uses ACE format cross sections, you
can use nuclear data that was processed with NJOY, such as that distributed with
MCNP_ or Serpent_.
Using JEFF Cross Sections from OECD/NEA
---------------------------------------
The NEA_ provides processed ACE data from the JEFF_ nuclear library upon
request. A DVD of the data can be requested here_. To use this data with OpenMC,
the following steps must be taken:
1. Copy and unzip the data on the DVD to a directory on your computer.
2. In the root directory, a file named ``xsdir``, or some variant thereof,
should be present. This file contains a listing of all the cross sections and
is used by MCNP. This file should be converted to a ``cross_sections.xml``
file for use with OpenMC. A Python script is provided in the OpenMC
distribution for this purpose:
.. code-block:: sh
openmc/src/utils/convert_xsdir.py xsdir31 cross_sections.xml
3. In the converted ``cross_sections.xml`` file, change the contents of the
<directory> element to the absolute path of the directory containing the
actual ACE files.
4. Additionally, you may need to change any occurrences of upper-case "ACE"
within the ``cross_sections.xml`` file to lower-case.
5. Either set the :ref:`cross_sections` in a settings.xml file or the
:envvar:`CROSS_SECTIONS` environment variable to the absolute path of the
``cross_sections.xml`` file.
Using Cross Sections from MCNP
------------------------------
To use cross sections distributed with MCNP, change the <directory> element in
the ``cross_sections.xml`` file in the root directory of the OpenMC distribution
to the location of the MCNP cross-sections. Then, either set the
to the location of the MCNP cross sections. Then, either set the
:ref:`cross_sections` in a settings.xml file or the :envvar:`CROSS_SECTIONS`
environment variable to the absolute path of the ``cross_sections.xml`` file.
Similarly, to use cross-sections distributed with Serpent, change the
<directory> element in the ``cross_sections_serpent.xml`` file in the root
directory of the OpenMC distribution to the location of the Serpent
cross-sections. Then, either set the :ref:`cross_sections` in a settings.xml
file or the :envvar:`CROSS_SECTIONS` environment variable to the absolute path
of the ``cross_sections_serpent.xml`` file.
Using Cross Sections from Serpent
---------------------------------
To use cross sections distributed with Serpent, change the <directory> element
in the ``cross_sections_serpent.xml`` file in the root directory of the OpenMC
distribution to the location of the Serpent cross sections. Then, either set the
:ref:`cross_sections` in a settings.xml file or the :envvar:`CROSS_SECTIONS`
environment variable to the absolute path of the ``cross_sections_serpent.xml``
file.
.. _NEA: http://www.oecd-nea.org
.. _JEFF: http://www.oecd-nea.org/dbdata/jeff/
.. _here: http://www.oecd-nea.org/dbdata/pubs/jeff312-cd.html
.. _MCNP: http://mcnp.lanl.gov
.. _Serpent: http://montecarlo.vtt.fi