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Python package for processing nuclear data distribution in ACE and ENDF format into HDF5 format for use in OpenMC. Adapted from the openmc data repo.

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test_urls test_package test_convert_scripts

OpenMC Data

Aims to facilitate the use of different nuclear data libraries with OpenMC by providing command line tools that process and download nuclear data automatically.

Prerequisites

You should have already installed OpenMC, see the docs for installation instructions.

Installation

The package is distributed on PYPI and can be installed with pip.

pip install openmc_data

Usage

Once installed several scripts are available in your terminal that are able to download and process nuclear data.

The scripts accept input arguments, to find out the input arguments available for a particular script run the script name with --help after the name. For example:

convert_endf --help

Some scripts (mainly the generate scripts) require NJOY to be installed and added to your path.

A few categories of scripts are available:

  • Scripts that produce h5 cross section files:
    • Convert ACE files to h5 files
    • Generate h5 file from ENDF files
    • Download h5 files
  • Scripts that produce xml chain files:
    • Generate xml chain files from ENDF files:
    • Download xml chain files:
  • Other scripts that don't fall into either category.

Produce Cross Section Files

Convert cross sections

Script name Library Release Processed by
convert_mcnp70 ENDF/B VII.0 LANL
convert_mcnp71 ENDF/B VII.1 LANL
convert_endf ENDF/B VII.1 NNDC
convert_lib80x ENDF/B VIII.0 LANL
convert_fendl FENDL 3.2b
3.2a
3.2
3.1d
3.1a
3.1
3.0
2.1
convert_jeff32 JEFF 3.2
convert_jeff33 JEFF 3.3
convert_tendl TENDL 2015
2017
2019
2021

Generate cross sections

Script name Library Release Processed by
generate_cendl CENDL 3.1
3.2
generate_endf ENDF/B VII.1
VIII.0
NNDC
generate_fendl FENDL 3.2b
3.2a
3.2
3.1d
3.1a
3.0
generate_jendl JENDL 4.0
5.0

Download cross sections

Script name Library Release Processed by
download_endf ENDF/B VII.1
VIII.0
NNDC
download_tendl TENDL 2019
2021

Produce Depletion Chain files

Generate chain files

Script name Library Release
generate_endf_chain ENDF/B VII.1
VIII.0
generate_jeff_chain JEFF 3.3
generate_jendl_chain JENDL 5.0
generate_tendl_chain TENDL 2019
2021
generate_serpent_fissq
generate_endf71_chain_casl ENDF/B

Download chain files

Script name Library Release Branching options
download_endf_chain ENDF/B VII.1
VIII.0
None
SFR
PWR

Other scripts

Script name Description
convert_tendl_rand Download random TENDL libraries from PSI and convert it to a HDF5 library for use with OpenMC. Only certain nuclides are available from PSI. This script generates a cross_sections_tendl.xml file with random TENDL evaluations plus a standard library located in 'OPENMC_CROSS_SECTIONS'
sample_sandy This scripts generates random (gaussian) evaluations of a nuclear data file following its covariance matrix using SANDY, and converts them to HDF5 for use in OpenMC. Script generates a cross_sections_sandy.xml file with the standard library plus the sampled evaluations.
make_compton
make_stopping_powers
add_branching_ratios add branching ratios for n,gamma reactions to a preexisting chain files.
reduce_chain
combine_libraries Combines multiple cross_section.xml files into a single cross_section.xml.

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Python package for processing nuclear data distribution in ACE and ENDF format into HDF5 format for use in OpenMC. Adapted from the openmc data repo.

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