From 5e4509fa53dcfc0f04a2d82996bfa2548bf48e97 Mon Sep 17 00:00:00 2001 From: Paul Romano Date: Wed, 9 Jan 2013 16:11:22 -0500 Subject: [PATCH] Added instructions on using JEFF ACE data from NEA. --- docs/source/usersguide/install.rst | 59 ++++++++++++++++++++++++------ 1 file changed, 48 insertions(+), 11 deletions(-) diff --git a/docs/source/usersguide/install.rst b/docs/source/usersguide/install.rst index fe50dd87f..05f08e064 100644 --- a/docs/source/usersguide/install.rst +++ b/docs/source/usersguide/install.rst @@ -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 + 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 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 - 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 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