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openmc-data-storage

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  1. openmc_data_downloader openmc_data_downloader Public

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

    Python 17 4

  2. material_xs_plotter material_xs_plotter Public

    XSPlot - Neutron cross section plotter for materials

    Python 3 3

  3. openmc_data 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.

    Python 19 3

  4. nuclide_cross_section_plotter.rs nuclide_cross_section_plotter.rs Public

    A Rust WASM based neutron cross section plotter for nuclides

    Rust 1 2

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