openmc-data 0.0.1

Collection of scripts for managing data for OpenMC

OpenMC Data Scripts

This repository contains a collection of scripts for generating HDF5 data libraries that can be used with OpenMC. Some of these scripts convert existing ACE libraries (such as those produced by LANL) whereas generate scripts use NJOY to process ENDF files directly

Note that unless you are interested in making a customized library, you can find pregenerated HDF5 libraries at https://openmc.org.

Another source of data libraries for OpenMC is the Windowed Multipole Library repository which enables on-the-fly Doppler broadening to an arbitrary temperature.

Prerequisites

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

Installation

Currently the package can be installed from this temporary repository.

pip install git+https://github.com/openmc-data-storage/openmc_data.git

In the future pip installing from PyPi or Conda could be provided

Usage

Once install several scripts are added to your python path 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_nndc71 --help

A few categories of scripts are available:

• Scripts that generate h5 cross section files for using in OpenMC from either ACE or ENDF files.
• Scripts that generate chain files for use in depletion simulations.
• Other scripts that don't fall into either category.

Cross Section

Script name	Library	Release	Processed by	Download available	Downloads ACE files and convert to HDF5	Downloads ENDF files and convert to HDF5	Convert local ACE files
generate_cendl	CENDL	3.1 3.2				:heavy_check_mark:
convert_mcnp70	ENDF/B	VII.0	LANL	openmc.org			:heavy_check_mark:
convert_mcnp71	ENDF/B	VII.1	LANL	openmc.org			:heavy_check_mark:
generate_endf	ENDF/B	VII.1	NNDC	openmc.org		:heavy_check_mark:
convert_nndc71	ENDF/B	VII.1	NNDC	openmc.org	:heavy_check_mark:	:heavy_check_mark:
convert_lib80x	ENDF/B	VIII.0	LANL	openmc.org			:heavy_check_mark:
generate_endf	ENDF/B	VIII.0	NNDC	openmc.org		:heavy_check_mark:
convert_fendl	FENDL	2.1 3.0 3.1a 3.1d 3.2		openmc.org 3.2	:heavy_check_mark:
generate_jendl	JENDL	4.0				:heavy_check_mark:
convert_jeff32	JEFF	3.2		openmc.org	:heavy_check_mark:
convert_jeff33	JEFF	3.3		openmc.org	:heavy_check_mark:
convert_tendl	TENDL	2015 2017 2019 2021			:heavy_check_mark:

Depletion Chains

Sctipt name	Library	Release	Download available	Download ENDF files and generates XML chain files
generate_endf71_chain_casl	ENDF/B	-	https://github.com/openmc-dev/data/tree/master/depletion	:heavy_check_mark:
generate_endf71_chain	ENDF/B	-	https://github.com/openmc-dev/data/tree/master/depletion	:heavy_check_mark:
generate_serpent_fissq	-	-	https://github.com/openmc-dev/data/tree/master/depletion	:heavy_check_mark:
generate_tendl_chain	TENDL	2019 2021	https://github.com/openmc-dev/data/tree/master/depletion	:heavy_check_mark:

Other scripts

Sctipt 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	Writes a depletion chain XML file from a depletion chain XML file and branching ratios
reduce_chain