Alternatives and similar repositories for MP-OFELIA:

Users that are interested in MP-OFELIA are comparing it to the libraries listed below

• eepeterson / openmc_fusion_benchmarks
  ☆18Updated last week
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated last month
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• Open-Sn / opensn
  open-source Sn software
  ☆27Updated this week
• ezsolti / RFP
  ☆30Updated last month
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 6 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆42Updated 2 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆40Updated 9 months ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆17Updated 4 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆31Updated 7 months ago
• jlball / arc-nonproliferation
  An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.
  ☆11Updated 6 months ago
• RemDelaporteMathurin / h-transport-materials
  Easily access hydrogen transport properties
  ☆15Updated 3 months ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated last month
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆13Updated this week
• festim-dev / FESTIM-workshop
  Learn how to simulate hydrogen transport with FESTIM
  ☆18Updated 3 months ago
• fusion-energy / cad_to_h5m
  Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API
  ☆12Updated last year
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆33Updated this week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆39Updated last month
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆56Updated 2 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated last week
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆11Updated 10 months ago
• openmc-data-storage / isotope-xs-plotter
  XSPlot - Neutron cross section plotter for isotopes
  ☆14Updated last year
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 2 years ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆38Updated 2 weeks ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆30Updated 2 months ago
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆28Updated last year
• 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 3 months ago
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆15Updated last week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year