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openmc-data-storage

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  1. openmc_data_downloaderopenmc_data_downloaderPublic

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

    Python 12 3

  2. material_xs_plottermaterial_xs_plotterPublic

    XSPlot - Neutron cross section plotter for materials

    Python 3 3

  3. openmc_dataopenmc_dataPublic

    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 7 2

  4. nuclide_cross_section_plotter.rsnuclide_cross_section_plotter.rsPublic

    A Rust WASM based neutron cross section plotter for nuclides

    Rust 1

Repositories

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Showing 10 of 23 repositories
  • openmc-data-storage/hdf5_nuclear_data_reader’s past year of commit activity
    Rust 10 2 1 UpdatedMar 5, 2025
  • nuclide_cross_section_plotter.rs Public

    A Rust WASM based neutron cross section plotter for nuclides

    openmc-data-storage/nuclide_cross_section_plotter.rs’s past year of commit activity
    Rust0MIT 1 0 0 UpdatedFeb 24, 2025
  • 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 1MIT0 2 0 UpdatedFeb 9, 2025
  • ENDF-B-VIII.0-NNDC-json Public

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

    openmc-data-storage/ENDF-B-VIII.0-NNDC-json’s past year of commit activity
    Python 3 1 1 0 UpdatedFeb 7, 2025
  • openmc-data-storage/FENDL-3.2c-json’s past year of commit activity
    Python0MIT0 0 0 UpdatedFeb 7, 2025
  • example_rust_wasm_yew_plotly_github_pages_website Public

    A prototype Rust WASM nuclear data plotter for nuclide cross sections

    openmc-data-storage/example_rust_wasm_yew_plotly_github_pages_website’s past year of commit activity
    Rust0MIT 1 3 2 UpdatedJan 30, 2025
  • 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 7MIT 2 2 0 UpdatedJan 12, 2025
  • openmc_data_downloader Public

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

    openmc-data-storage/openmc_data_downloader’s past year of commit activity
    Python 12MIT 3 6(1 issue needs help) 0 UpdatedJan 9, 2025
  • ace_to_h5_file_converter Public

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

    openmc-data-storage/ace_to_h5_file_converter’s past year of commit activity
    Python00 0 0 UpdatedNov 1, 2023
  • cross_section_comparison Public

    Compare nuclear interaction cross sections for different libraries

    openmc-data-storage/cross_section_comparison’s past year of commit activity
    HTML0MIT 1 1 0 UpdatedOct 31, 2023

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