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
  ☆26Updated last month
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆59Updated 5 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
• mit-crpg / openmc-reactor-examples
  Catalogs a plethora of reactor inputs for OpenMC
  ☆26Updated 4 months ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆43Updated last month
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆18Updated 7 months ago
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated 3 weeks ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆59Updated 3 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆111Updated last month
• paulromano / endf-python
  Python ENDF Parser
  ☆34Updated 11 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆71Updated 3 weeks ago
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆17Updated last week
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated this week
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆47Updated this week
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆45Updated this week
• IAEA-NDS / open-benchmarks
  Computational inputs, reference outputs and experimental data for V&V systems
  ☆13Updated 3 months ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆39Updated last month
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated this week
• Open-Sn / opensn
  open-source Sn software
  ☆36Updated this week
• ezsolti / RFP
  ☆31Updated 3 weeks ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆32Updated 3 weeks ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆79Updated last year
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated 2 years ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆112Updated 5 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…
  ☆40Updated 7 months ago
• lanl / mcnptools
  ☆82Updated last year
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆22Updated 2 months ago
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆54Updated 9 months ago
• openmsr / msr-archive
  curated documents pertaining to early molten salt reactor research.
  ☆22Updated last year
• 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…
  ☆155Updated this week