mirror of
https://github.com/openmc-dev/openmc.git
synced 2026-07-27 13:45:36 -04:00
Merge branch 'master' into KappFiss
Conflicts: src/constants.F90 src/tally.F90 src/utils/statepoint.py
This commit is contained in:
Paul Romano
commit
e0978a80ea
9 changed files with 503 additions and 102 deletions
|
|
@ -126,11 +126,33 @@ This will build an executable named ``openmc``.
|
|||
Compiling on Windows
|
||||
--------------------
|
||||
|
||||
To compile OpenMC on a Windows operating system, you will need to first install
|
||||
Cygwin_, a Linux-like environment for Windows. When configuring Cygwin, make
|
||||
sure you install both the gfortran compiler as well as git. Once you have
|
||||
obtained the source code, run the following commands from within the source code
|
||||
root directory:
|
||||
Using Cygwin
|
||||
------------
|
||||
|
||||
One option for compiling OpenMC on a Windows operating system is to use Cygwin_,
|
||||
a Linux-like environment for Windows. You will need to first `install
|
||||
Cygwin`_. When you are asked to select packages, make sure the following are
|
||||
selected:
|
||||
|
||||
* Devel: gcc4-core
|
||||
* Devel: gcc4-fortran
|
||||
* Devel: make
|
||||
|
||||
If you plan on obtaining the source code directly using git, select the
|
||||
following packages:
|
||||
|
||||
* Devel: git
|
||||
* Devel: git-completion (Optional)
|
||||
* Devel: gitk (Optional)
|
||||
|
||||
In order to use the Python scripts provided with OpenMC, you will also need to
|
||||
install Python. This can be done within Cygwin or directly in Windows. To
|
||||
install within Cygwin, select the following packages:
|
||||
|
||||
* Python: python (Version > 2.7 recommended)
|
||||
|
||||
Once you have obtained the source code, run the following commands from within
|
||||
the source code root directory:
|
||||
|
||||
.. code-block:: sh
|
||||
|
||||
|
|
@ -139,29 +161,93 @@ root directory:
|
|||
|
||||
This will build an executable named ``openmc``.
|
||||
|
||||
.. _Cygwin: http://www.cygwin.com/
|
||||
.. _Cygwin: http://cygwin.com/
|
||||
.. _install Cygwin: http://cygwin.com/setup.exe
|
||||
|
||||
Using MinGW
|
||||
-----------
|
||||
|
||||
An alternate option for installing OpenMC on Windows is using MinGW_, which
|
||||
stands for Minimalist GNU for Windows. An executable for installing the MinGW
|
||||
distribution is available on SourceForge_. When installing MinGW, make sure the
|
||||
following components are selected:
|
||||
|
||||
* MinGW Compiler Suite: Fortran Compiler
|
||||
* MSYS Basic System
|
||||
|
||||
Once MinGW is installed, copy the OpenMC source distribution to your MinGW home
|
||||
directory (usually C:\\MinGW\\msys\\1.0\\home\\YourUsername). Once you have
|
||||
the source code in place, run the following commands from within the MinGW shell
|
||||
in the root directory of the OpenMC distribution:
|
||||
|
||||
.. code-block:: sh
|
||||
|
||||
cd src
|
||||
make
|
||||
|
||||
This will build an executable named ``openmc``.
|
||||
|
||||
.. _MinGW: http://www.mingw.org
|
||||
.. _SourceForge: http://sourceforge.net/projects/mingw
|
||||
|
||||
---------------------------
|
||||
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
|
||||
|
||||
|
|
|
|||
Loading…
Add table
Add a link
Reference in a new issue