crp/OpenMC
1
0
Fork 0
mirror of https://github.com/openmc-dev/openmc.git synced 2026-07-27 05:35:49 -04:00
Code Issues Projects Releases Packages Wiki Activity Actions

Changes suggested by @liangjg

Browse source
This commit is contained in:
Paul Romano 2018-11-13 10:52:53 -06:00
parent 927cbdac14
commit 0abb03fdc9
2 changed files with 7 additions and 6 deletions
Download patch file Download diff file Expand all files Collapse all files

3
Dockerfile
View file

@ -5,7 +5,6 @@ ENV FC=/usr/bin/mpif90 CC=/usr/bin/mpicc CXX=/usr/bin/mpicxx \
PATH=/opt/openmc/bin:/opt/NJOY2016/build:$PATH \
LD_LIBRARY_PATH=/opt/openmc/lib:$LD_LIBRARY_PATH \
OPENMC_CROSS_SECTIONS=/root/nndc_hdf5/cross_sections.xml \
OPENMC_MULTIPOLE_LIBRARY=/root/WMP_Library \
OPENMC_ENDF_DATA=/root/endf-b-vii.1
# Install dependencies from Debian package manager
@ -36,4 +35,4 @@ RUN git clone https://github.com/openmc-dev/openmc.git /opt/openmc && \
cd .. && pip install -e .[test]
# Download cross sections (NNDC and WMP) and ENDF data needed by test suite
RUN ./opt/openmc/tools/ci/download-xs.sh
RUN ./opt/openmc/tools/ci/download-xs.sh

10
docs/source/io_formats/cross_sections.rst
View file

@ -25,9 +25,10 @@ node. For example,
``<library>`` Element
---------------------
The ``<library>`` element indicates where an HDF5 cross section file is located,
whether it contains incident neutron or thermal scattering data, and what
materials are listed within. It has the following attributes:
The ``<library>`` element indicates where an HDF5 data file is located, whether
it contains incident neutron, incident photon, thermal scattering, or windowed
multipole data, and what materials are listed within. It has the following
attributes:
:materials:
@ -48,4 +49,5 @@ materials are listed within. It has the following attributes:
directory containing the ``cross_sections.xml`` file.
:type:
The type of data contained in the file, either 'neutron' or 'thermal'.
The type of data contained in the file. Accepted values are 'neutron',
'thermal', 'photon', and 'wmp'.