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Update scripts section, fix bugs in openmc-plot-mesh-tally
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Paul Romano
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7 changed files with 187 additions and 114 deletions
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@ -45,46 +45,182 @@ flags:
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-v, --version Show version information
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-h, --help Show help message
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.. _scripts_ace:
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----------------------
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``openmc-ace-to-hdf5``
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----------------------
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This script can be used to create HDF5 nuclear data libraries used by OpenMC if
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you have existing ACE files. There are four different ways you can specify ACE
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libraries that are to be converted:
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1. List each ACE library as a positional argument. This is very useful in
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conjunction with the usual shell utilities (ls, find, etc.).
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2. Use the ``--xml`` option to specify a pre-v0.9 cross_sections.xml file.
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3. Use the ``--xsdir`` option to specify a MCNP xsdir file.
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4. Use the ``--xsdata`` option to specify a Serpent xsdata file.
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The script does not use any extra information from cross_sections.xml/ xsdir/
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xsdata files to determine whether the nuclide is metastable. Instead, the
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``--metastable`` argument can be used to specify whether the ZAID naming convention
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follows the NNDC data convention (1000*Z + A + 300 + 100*m), or the MCNP data
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convention (essentially the same as NNDC, except that the first metastable state
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of Am242 is 95242 and the ground state is 95642).
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The optional ``--fission_energy_release`` argument will accept an HDF5 file
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containing a library of fission energy release (ENDF MF=1 MT=458) data. A
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library built from ENDF/B-VII.1 data is released with OpenMC and can be found at
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openmc/data/fission_Q_data_endb71.h5. This data is necessary for
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'fission-q-prompt' and 'fission-q-recoverable' tallies, but is not needed
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otherwise.
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-h, --help show help message and exit
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-d DESTINATION, --destination DESTINATION
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Directory to create new library in (default: .)
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-m META, --metastable META
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How to interpret ZAIDs for metastable nuclides. META
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can be either 'nndc' or 'mcnp'. (default: nndc)
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--xml XML Old-style cross_sections.xml that lists ACE libraries
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--xsdir XSDIR MCNP xsdir file that lists ACE libraries
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--xsdata XSDATA Serpent xsdata file that lists ACE libraries
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--fission_energy_release FISSION_ENERGY_RELEASE
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HDF5 file containing fission energy release data
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.. _scripts_mcnp70:
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------------------------------
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``openmc-convert-mcnp70-data``
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------------------------------
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This script converts ENDF/B-VII.0 ACE data from the MCNP5/6 distribution into an
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HDF5 library that can be used by OpenMC. This assumes that you have a directory
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containing files named endf70a, endf70b, ..., endf70k, and endf70sab. The path
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to the directory containing these files should be given as a positional
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argument. The following optional arguments are available:
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-d DESTINATION, --destination DESTINATION
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Directory to create new library in (Default: mcnp_endfb70)
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.. _scripts_mcnp71:
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------------------------------
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``openmc-convert-mcnp71-data``
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------------------------------
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This script converts ENDF/B-VII.1 ACE data from the MCNP6 distribution into an
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HDF5 library that can be used by OpenMC. This assumes that you have a directory
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containing subdirectories 'endf71x' and 'ENDF71SaB'. The path to the directory
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containing these subdirectories should be given as a positional argument. The
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following optional arguments are available:
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-d DESTINATION, --destination DESTINATION
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Directory to create new library in (Default: mcnp_endfb71)
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-f FER, --fission_energy_release FER
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HDF5 file containing fission energy release data
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.. _scripts_jeff:
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------------------------
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``openmc-get-jeff-data``
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------------------------
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This script downloads `JEFF 3.2 ACE data
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<https://www.oecd-nea.org/dbforms/data/eva/evatapes/jeff_32/>`_ from OECD/NEA
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and converts it to a multi-temperature HDF5 library for use with OpenMC. It has
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the following optional arguments:
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-b, --batch
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Suppress standard in
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-d DESTINATION, --destination DESTINATION
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Directory to create new library in (default: jeff-3.2-hdf5)
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.. warning:: This script will download approximately 9 GB of data. Extracting
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and processing the data may require as much as 40 GB of additional
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free disk space.
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-----------------------------
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``openmc-get-multipole-data``
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-----------------------------
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This script downloads and extracts windowed multipole data based on
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ENDF/B-VII.1. It has the following optional arguments:
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-b, --batch Suppress standard in
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.. _scripts_nndc:
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------------------------
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``openmc-get-nndc-data``
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------------------------
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This script downloads `ENDF/B-VII.1 ACE data
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<http://www.nndc.bnl.gov/endf/b7.1/acefiles.html>`_ from NNDC and converts it to
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an HDF5 library for use with OpenMC. This data is used for OpenMC's regression
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test suite. This script has the following optional arguments:
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-b, --batch Suppress standard in
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--------------------------
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``openmc-plot-mesh-tally``
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--------------------------
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``openmc-plot-mesh-tally`` provides a graphical user interface for plotting mesh
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tallies. The path to the statepoint file can be provided as an optional arugment
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(if omitted, a file dialog will be presented).
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-----------------------
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``openmc-track-to-vtk``
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-----------------------
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This script converts HDF5 particle track files to VTK poly data that can be
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viewed with ParaView or VisIt. The filenames of the particle track files should
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be given as posititional arguments. The output filename can also be changed with
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the ``-o`` flag:
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-o OUT, --out OUT Output VTK poly filename
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------------------------
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``openmc-update-inputs``
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------------------------
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If you have existing XML files that worked in a previous version of OpenMC that
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no longer work with the current version, you can try to update these files using
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``openmc-update-inputs``. If any of the given files do not match the most
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up-to-date formatting, then they will be automatically rewritten. The old
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out-of-date files will not be deleted; they will be moved to a new file with
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'.original' appended to their name.
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Formatting changes that will be made:
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geometry.xml
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Lattices containing 'outside' attributes/tags will be replaced with lattices
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containing 'outer' attributes, and the appropriate cells/universes will be
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added. Any 'surfaces' attributes/elements on a cell will be renamed 'region'.
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materials.xml
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Nuclide names will be changed from ACE aliases (e.g., Am-242m) to HDF5/GND
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names (e.g., Am242_m1). Thermal scattering table names will be changed from
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ACE aliases (e.g., HH2O) to HDF5/GND names (e.g., c_H_in_H2O).
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----------------------
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``openmc-update-mgxs``
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----------------------
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This script updates OpenMC's deprecated multi-group cross section XML files to
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the latest HDF5-based format.
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-i IN, --input IN Input XML file
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-o OUT, --output OUT Output file in HDF5 format
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.. _scripts_validate:
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-----------------------
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