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A Python package for downloading h5 cross section files for use in OpenMC.
Python
17
4
XSPlot - Neutron cross section plotter for materials
Python
3
3
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.
Python
21
5
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Showing 10 of 23 repositories
openmc_data
Public
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.
openmc-data-storage/openmc_data's past year of commit activity
Python
21
MIT
5
5
0
Updated Nov 3, 2026
openmc-data-storage/TENDL-2025's past year of commit activity
0
MIT
0
0
0
Updated Jul 24, 2026
openmc-data-storage/openmc_data_downloader's past year of commit activity
openmc-data-storage/ENDF-B-VIII.1-NNDC's past year of commit activity
0
MIT
0
0
0
Updated Jul 8, 2026
openmc_data_to_json
Public
Converts h5 cross section files into seperate json files for individual reaction.
openmc-data-storage/openmc_data_to_json's past year of commit activity
Python
1
MIT
0
3
0
Updated Aug 6, 2025
openmc-data-storage/ENDF-B-VIII.0-NNDC-json's past year of commit activity
Python
3
1
1
0
Updated Feb 7, 2025
openmc-data-storage/FENDL-3.2c-json's past year of commit activity
Python
0
MIT
0
0
0
Updated Feb 7, 2025
openmc-data-storage/example_rust_wasm_yew_plotly_github_pages_website's past year of commit activity
Rust
0
MIT
1
3
2
Updated Jan 30, 2025
openmc-data-storage/ace_to_h5_file_converter's past year of commit activity
Python
0
0
0
0
Updated Nov 1, 2023
openmc-data-storage/cross_section_comparison's past year of commit activity
HTML
0
MIT
1
1
0
Updated Oct 31, 2023
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