Alternatives and similar repositories for benchmarks:

Users that are interested in benchmarks are comparing it to the libraries listed below

• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆39Updated 6 months ago
• eepeterson / openmc_fusion_benchmarks
  ☆18Updated 5 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆22Updated 4 months ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated 4 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆25Updated this week
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆29Updated last year
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆38Updated 3 weeks ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆33Updated 2 weeks ago
• paulromano / endf-python
  Python ENDF Parser
  ☆27Updated 5 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆54Updated last month
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆37Updated 3 weeks ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆25Updated 4 months ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆13Updated 7 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆59Updated 3 weeks ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆64Updated last year
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆11Updated 8 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆49Updated last week
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆22Updated 3 months ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆105Updated last week
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆32Updated last month
• mit-crpg / openmc-workshop
  Contains slides and example problems for OpenMC workshops and presentations
  ☆23Updated 2 years ago
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆35Updated 2 months ago
• svalinn / Cubit-plugin
  Plugins and command extensions for Coreform Cubit
  ☆18Updated 7 months 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
• 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…
  ☆39Updated last month
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆25Updated 3 weeks 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