https://github.com/openmc-data-storage/openmc_data
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.
https://github.com/openmc-data-storage/openmc_data
Last synced: 4 months ago
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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.
- Host: GitHub
- URL: https://github.com/openmc-data-storage/openmc_data
- Owner: openmc-data-storage
- License: mit
- Created: 2024-01-27T21:23:38.000Z (over 2 years ago)
- Default Branch: main
- Last Pushed: 2026-02-04T20:40:29.000Z (5 months ago)
- Last Synced: 2026-02-05T08:32:02.856Z (5 months ago)
- Language: Python
- Size: 9.93 MB
- Stars: 16
- Watchers: 3
- Forks: 2
- Open Issues: 5
-
Metadata Files:
- Readme: README.md
- License: LICENSE
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# 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](https://docs.openmc.org/en/stable/quickinstall.html) for installation instructions.
# Installation
The package is distributed on [PYPI](https://pypi.org/project/openmc-data/) and can be installed with pip.
```bash
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](https://github.com/njoy/NJOY2016) 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 | 3.2c
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 | 3.2c
3.2b
3.2a
3.2
3.1d
3.1a
3.0 | |
| generate_jendl | JENDL | 4.0
5.0 | |
| generate_tendl | TENDL | 2023
2025 | |
### 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_chain | ENDF/B
TENDL | VII.1
VIII.0
2019 | None
SFR
PWR
FNS |
## 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. |