Alternatives and similar repositories for neutronics-workshop

Users that are interested in neutronics-workshop are comparing it to the libraries listed below

• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆60Updated last week
• 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-ecosystem
  List of open source projects related to OpenMC
  ☆27Updated 2 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated 2 weeks ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆48Updated this week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆39Updated 3 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆35Updated 2 weeks ago
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆119Updated 2 weeks ago
• openmc-dev / openmc-notebooks
  Example Jupyter notebooks for OpenMC
  ☆37Updated 6 months ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆114Updated 6 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆74Updated 2 months ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated last month
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆44Updated 3 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
  ☆61Updated 4 months ago
• stellarmesh / stellarmesh
  Meshing library for nuclear workflows
  ☆50Updated last week
• fusion-energy / paramak
  Create parametric 3D fusion reactor CAD and neutronics models
  ☆87Updated 3 weeks ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆18Updated 3 weeks ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆39Updated 3 weeks ago
• Open-Sn / opensn
  open-source Sn software
  ☆39Updated this week
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆32Updated 2 months ago
• lanl / mcnptools
  ☆84Updated last year
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated last week
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆33Updated last month
• ezsolti / RFP
  ☆32Updated last month
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆66Updated 2 years ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated 3 weeks ago
• fispact / pypact
  A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact
  ☆30Updated 3 weeks ago