Alternatives and similar repositories for BEAVRS:

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

• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 7 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆39Updated last month
• mit-crpg / openmc-reactor-examples
  Catalogs a plethora of reactor inputs for OpenMC
  ☆23Updated last month
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• paulromano / endf-python
  Python ENDF Parser
  ☆31Updated 8 months ago
• eepeterson / openmc_fusion_benchmarks
  ☆19Updated last week
• 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 / plotter
  Native plotting GUI for model design and verification
  ☆57Updated 2 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆42Updated 2 months ago
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆13Updated this week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆17Updated 4 months ago
• openmsr / msr-archive
  curated documents pertaining to early molten salt reactor research.
  ☆22Updated last year
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆63Updated this week
• lanl / mcnptools
  ☆77Updated 10 months ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆39Updated this week
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated last month
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆52Updated 5 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆27Updated this week
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆29Updated 2 months ago
• ezsolti / RFP
  ☆30Updated last month
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆40Updated this week
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆104Updated last month
• 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 / data
  Collection of scripts for managing data for OpenMC
  ☆30Updated 2 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆25Updated this week
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated 2 months ago
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆15Updated last week
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆28Updated last year