Alternatives and similar repositories for NJOY21:

Users that are interested in NJOY21 are comparing it to the libraries listed below

• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆103Updated last month
• lanl / mcnptools
  ☆76Updated 9 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆55Updated 2 weeks ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆60Updated last week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆37Updated 2 weeks ago
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 2 years ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆37Updated last week
• paulromano / endf-python
  Python ENDF Parser
  ☆28Updated 7 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆50Updated last month
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆33Updated 2 months ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆37Updated this week
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆15Updated last month
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 6 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆55Updated last month
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆109Updated 2 weeks ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆40Updated last month
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆14Updated last month
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆20Updated 2 years ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated last month
• mctools / ncrystal
  NCrystal : a library for thermal neutron transport in crystals and other materials
  ☆44Updated this week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆29Updated last month
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆28Updated last month
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆26Updated last year
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆25Updated this week
• ezsolti / RFP
  ☆30Updated last week
• mit-crpg / openmc-reactor-examples
  Catalogs a plethora of reactor inputs for OpenMC
  ☆23Updated this week
• openmsr / msr-archive
  curated documents pertaining to early molten salt reactor research.
  ☆22Updated 11 months ago