Alternatives and similar repositories for MCDC

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

• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆34Updated 8 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆36Updated last month
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆67Updated 2 years ago
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆21Updated 2 years ago
• openmc-dev / validation
  Collection of validation scripts, notebooks, results
  ☆11Updated last year
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆116Updated 7 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆60Updated 3 weeks ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆27Updated 3 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated this week
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated 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…
  ☆41Updated 9 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆51Updated 3 weeks ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 2 months ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆32Updated 2 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆42Updated this week
• ukaea / neutronics_material_maker
  A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak
  ☆19Updated 4 years ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 2 years ago
• mctools / ncrystal
  NCrystal : a library for thermal neutron transport in crystals and other materials
  ☆46Updated last week
• arfc / moltres
  Repository for Moltres, a code for simulating Molten Salt Reactors
  ☆73Updated 2 weeks ago
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆30Updated last month
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated 3 weeks ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆18Updated 7 months ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated 3 weeks ago
• svalinn / parastell
  Parametric 3-D modeling toolset for stellarator fusion devices
  ☆34Updated this week
• arjankoning1 / talys
  The nuclear reaction model code
  ☆43Updated this week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 4 years ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆45Updated last week
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆37Updated 2 months ago
• svalinn / ALARA
  Simulation of transmutation and decay in nuclear systems
  ☆29Updated last week
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆54Updated 11 months ago