openmc-data-storage

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.

A Python package for downloading h5 cross section files for use in OpenMC.

A Rust WASM based neutron cross section plotter for nuclides

Converts h5 cross section files into seperate json files for individual reaction.

A collection of json file for each nuclide and reaction in the nuclear data library

A prototype Rust WASM nuclear data plotter for nuclide cross sections

Check Nuclear data ACE files converts to h5 format for use in OpenMC