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
  ☆64Updated last month
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆30Updated 6 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆53Updated last week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 7 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 2 months ago
• openmc-dev / openmc-notebooks
  Example Jupyter notebooks for OpenMC
  ☆40Updated 10 months ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆40Updated this week
• lanl / mcnptools
  ☆87Updated last year
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆118Updated 10 months ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆52Updated 2 weeks ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆83Updated 3 weeks ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated this week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆22Updated 2 weeks ago
• Open-Sn / opensn
  Open-source Sn software
  ☆52Updated last week
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆120Updated last week
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated 2 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆34Updated last week
• ezsolti / RFP
  ☆33Updated 5 months ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆33Updated 6 months ago
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last week
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆18Updated 2 weeks ago
• mit-crpg / openmc-reactor-examples
  Catalogs a plethora of reactor inputs for OpenMC
  ☆35Updated 10 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆14Updated 7 months ago
• fusion-energy / paramak
  Create parametric 3D fusion reactor CAD and neutronics models
  ☆89Updated 3 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆122Updated 2 weeks ago
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆39Updated 6 months ago