Alternatives and similar repositories for openmc-workshop

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

• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆55Updated 3 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• 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…
  ☆175Updated this week
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆30Updated 8 months ago
• openmc-dev / openmc-notebooks
  Example Jupyter notebooks for OpenMC
  ☆42Updated 11 months ago
• mit-crpg / OpenMOC
  A method of characteristics code for nuclear reactor physics calculations.
  ☆178Updated last year
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆40Updated last month
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆52Updated last month
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 4 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆64Updated last week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 8 months ago
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated 2 years ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆51Updated this week
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last week
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆14Updated 8 months ago
• mit-crpg / openmc-reactor-examples
  Catalogs a plethora of reactor inputs for OpenMC
  ☆35Updated 11 months ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆33Updated 7 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆85Updated last month
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated this week
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆38Updated last month
• lanl / mcnptools
  ☆87Updated last year
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆123Updated last week
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated 2 years ago
• ezsolti / RFP
  ☆33Updated 6 months ago
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆58Updated 4 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆123Updated last week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆23Updated 2 weeks ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 2 weeks ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆24Updated last year