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
  ☆21Updated last week
• Open-Sn / opensn
  open-source Sn software
  ☆29Updated this week
• RemDelaporteMathurin / h-transport-materials
  Easily access hydrogen transport properties
  ☆15Updated 3 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆25Updated 7 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆42Updated this week
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• ezsolti / RFP
  ☆30Updated 2 months ago
• festim-dev / FESTIM-workshop
  Learn how to simulate hydrogen transport with FESTIM
  ☆18Updated this week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆17Updated 5 months ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated this week
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆17Updated 2 years ago
• elementx54 / moosefw_vim
  Vim plugin for MOOSE Framework input file format
  ☆12Updated last year
• paulromano / endf-python
  Python ENDF Parser
  ☆32Updated 8 months ago
• festim-dev / FESTIM
  Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS
  ☆101Updated this week
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆40Updated 9 months ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆33Updated 3 weeks ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆57Updated 3 months ago
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆15Updated 2 weeks ago
• mohamedlahdour / OpenNTP
  In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.
  ☆11Updated 4 years ago
• SlaybaughLab / BART
  A deterministic finite-element-based solver for the neutron transport equation designed for the evaluation of acceleration methods.
  ☆26Updated 3 years ago
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆65Updated last year
• idaholab / virtual_test_bed
  The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
  ☆53Updated this week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆40Updated 2 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
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆30Updated last week
• jlball / arc-nonproliferation
  An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.
  ☆11Updated 7 months ago
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆52Updated 6 months ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆31Updated 3 months ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated 2 months ago