Alternatives and similar repositories for neutronics-workshop:

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

• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆59Updated last month
• openmc-dev / openmc-notebooks
  Example Jupyter notebooks for OpenMC
  ☆35Updated 2 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆55Updated 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
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆53Updated 7 months ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆37Updated last month
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆25Updated this week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• lanl / mcnptools
  ☆73Updated 8 months ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆106Updated last week
• fusion-energy / paramak
  Create parametric 3D fusion reactor CAD and neutronics models
  ☆73Updated 3 weeks ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆33Updated 3 weeks ago
• paulromano / endf-python
  Python ENDF Parser
  ☆27Updated 5 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆39Updated this week
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆49Updated 3 weeks ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆36Updated 3 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆23Updated 5 months ago
• stellarmesh / stellarmesh
  Meshing library for nuclear workflows
  ☆45Updated 2 months ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆34Updated this week
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆99Updated this week
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 2 years ago
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆31Updated last month
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆39Updated 7 months ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆77Updated last year
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆26Updated 11 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆101Updated this week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• eepeterson / openmc_fusion_benchmarks
  ☆18Updated 5 months ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆30Updated 11 months ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆13Updated 8 months ago