openmc-data-storage's repositories
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.
isotope-xs-plotter
XSPlot - Neutron cross section plotter for isotopes
openmc_data_downloader
A Python package for downloading h5 cross section files for use in OpenMC.
ENDF-B-VIII.0-NNDC-json
A collection of json file for each nuclide and reaction in the nuclear data library
material_xs_plotter
XSPlot - Neutron cross section plotter for materials
ENDF-B-VII.1-NNDC
Nuclear data from the ENDF-B-VII.1 NNDC library processed in the OpenMC h5 file format
nuclide_cross_section_plotter.rs
A Rust WASM based neutron cross section plotter for nuclides
openmc_data_to_json
Converts h5 cross section files into seperate json files for individual reaction.
ace_to_h5_file_converter
Check Nuclear data ACE files converts to h5 format for use in OpenMC
cross_section_comparison
Compare nuclear interaction cross sections for different libraries
dockerfiles_with_nuclear_data
Dockerfiles based on MiniConda with nuclear data in the first layer
ENDF-B-VII.1-WMP
Windowed Multipole Library
example_rust_wasm_yew_plotly_github_pages_website
A prototype Rust WASM nuclear data plotter for nuclide cross sections
isotope_xs_plotter_pyscript
A webpage for plotting isotope cross sections that makes use of PyScript
nuc_data_processing_template
This is a template repo for building nuclear data
nuclear_data_base_docker
A Dockerfile for containing separate JSON files split into individual reactions for a range of libraries
openmc_cross_section_plotter
A Python package for creating interactive OpenMC cross sections plots.
TENDL-2019
Nuclear data from the TENDL 2019 library processed in the OpenMC h5 file format