openmc-data-storage

Pinned Repositories

dockerfiles_with_nuclear_data
Dockerfiles based on MiniConda with nuclear data in the first layer
Language:Dockerfile0 2 10
ENDF-B-VIII.0-NNDC-json
A collection of json file for each nuclide and reaction in the nuclear data library
Language:Python3 2 11
hdf5_nuclear_data_reader
Language:Rust10
isotope-xs-plotter
XSPlot - Neutron cross section plotter for isotopes
Language:Python14 1 141
material_xs_plotter
XSPlot - Neutron cross section plotter for materials
Language:Python3 1 63
nuclide_cross_section_plotter.rs
A Rust WASM based neutron cross section plotter for nuclides
Language:Rust01
openmc_cross_section_plotter
A Python package for creating interactive OpenMC cross sections plots.
0 2 00
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.
Language:Python12 3 42
openmc_data_downloader
A Python package for downloading h5 cross section files for use in OpenMC.
Language:Python14 1 73
openmc_data_to_json
Converts h5 cross section files into seperate json files for individual reaction.
Language:Python1 3 50

openmc-data-storage's Repositories

openmc-data-storage/isotope-xs-plotter
XSPlot - Neutron cross section plotter for isotopes
Language:Python14 1 141
openmc-data-storage/openmc_data_downloader
A Python package for downloading h5 cross section files for use in OpenMC.
Language:Python14 1 73
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.
Language:Python12 3 42
openmc-data-storage/ENDF-B-VIII.0-NNDC-json
A collection of json file for each nuclide and reaction in the nuclear data library
Language:Python3 2 11
openmc-data-storage/material_xs_plotter
XSPlot - Neutron cross section plotter for materials
Language:Python3 1 63
openmc-data-storage/hdf5_nuclear_data_reader
Language:Rust10
openmc-data-storage/openmc_data_to_json
Converts h5 cross section files into seperate json files for individual reaction.
Language:Python1 3 50
openmc-data-storage/ace_to_h5_file_converter
Check Nuclear data ACE files converts to h5 format for use in OpenMC
Language:Python0 2 00
openmc-data-storage/cross_section_comparison
Compare nuclear interaction cross sections for different libraries
Language:HTML0 2 11
openmc-data-storage/dockerfiles_with_nuclear_data
Dockerfiles based on MiniConda with nuclear data in the first layer
Language:Dockerfile0 2 10
openmc-data-storage/ENDF-B-VII.1-NNDC
Nuclear data from the ENDF-B-VII.1 NNDC library processed in the OpenMC h5 file format
Language:Python0 3 00
openmc-data-storage/ENDF-B-VII.1-WMP
Windowed Multipole Library
Language:Python0 1 00
openmc-data-storage/ENDF-B-VIII.0-NNDC
Language:Python0 2 00
openmc-data-storage/example_rust_wasm_yew_plotly_github_pages_website
A prototype Rust WASM nuclear data plotter for nuclide cross sections
Language:Rust0 1 31
openmc-data-storage/FENDL-3.1d
Language:Python0 2 00
openmc-data-storage/isotope_xs_plotter_pyscript
A webpage for plotting isotope cross sections that makes use of PyScript
Language:HTML0 2 00
openmc-data-storage/JEFF-3.2
Nuclear data from the JEFF-3.3 library process in the OpenMC h5 file format
Language:Python0 3 00
openmc-data-storage/nuc_data_processing_template
This is a template repo for building nuclear data
Language:Python0 3 00
openmc-data-storage/nuclear_data_base_docker
A Dockerfile for containing separate JSON files split into individual reactions for a range of libraries
Language:Python0 3 20
openmc-data-storage/nuclide_cross_section_plotter.rs
A Rust WASM based neutron cross section plotter for nuclides
Language:Rust01
openmc-data-storage/openmc_cross_section_plotter
A Python package for creating interactive OpenMC cross sections plots.
0 2 00
openmc-data-storage/TENDL-2019
Nuclear data from the TENDL 2019 library processed in the OpenMC h5 file format
Language:Python0 2 00
openmc-data-storage/FENDL-3.2c-json
Language:Python