Alternatives and similar repositories for NJOY2016

Users that are interested in NJOY2016 are comparing it to the libraries listed below

• njoy / NJOY21
  NJOY for the 21st Century
  ☆80Updated last year
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆116Updated 7 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 5 months ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆39Updated 2 weeks ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆46Updated this week
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆51Updated 3 weeks ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 4 years ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆60Updated last month
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆39Updated 3 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆27Updated 3 months ago
• lanl / mcnptools
  ☆85Updated last year
• paulromano / endf-python
  Python ENDF Parser
  ☆36Updated last month
• mit-crpg / OpenMOC
  A method of characteristics code for nuclear reactor physics calculations.
  ☆167Updated last year
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated this week
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated this week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆77Updated 2 months ago
• njoy / ACEtk
  Toolkit for working with ACE-formatted data files
  ☆30Updated 2 weeks ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated last week
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆18Updated 10 months ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 2 months ago
• ezsolti / RFP
  ☆32Updated 2 months ago
• 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…
  ☆41Updated 9 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆42Updated last week
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆22Updated 3 years ago
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆65Updated 2 years ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆32Updated last week
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆30Updated last month
• fusion-energy / neutronics-workshop
  A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…
  ☆159Updated last month
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆35Updated 8 months ago