Alternatives and similar repositories for data:

Users that are interested in data are comparing it to the libraries listed below

• openmc-dev / validation
  Collection of validation scripts, notebooks, results
  ☆11Updated last year
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated last week
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆42Updated 2 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆57Updated 2 months ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated 2 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 7 months ago
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆18Updated last year
• eepeterson / openmc_fusion_benchmarks
  ☆19Updated last week
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆40Updated 9 months ago
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆33Updated 3 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆31Updated 8 months ago
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆52Updated 5 months ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆23Updated 6 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆25Updated this week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆40Updated last month
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆56Updated last month
• openmc-dev / openmc-notebooks
  Example Jupyter notebooks for OpenMC
  ☆37Updated last month
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆32Updated 3 weeks ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated 2 months ago
• svalinn / Cubit-plugin
  Plugins and command extensions for Coreform Cubit
  ☆18Updated 9 months ago
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆21Updated 2 years ago
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆11Updated 10 months ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆39Updated this week
• jlanversin / ONIX
  ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…
  ☆39Updated 3 months ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆17Updated 4 months ago
• fusion-energy / cad_to_h5m
  Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API
  ☆12Updated last year