Alternatives and similar repositories for NE250

Users that are interested in NE250 are comparing it to the libraries listed below

• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 2 months ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆118Updated 10 months ago
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆57Updated 3 months ago
• arfc / moltres
  Repository for Moltres, a code for simulating Molten Salt Reactors
  ☆76Updated 2 weeks ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆38Updated this week
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆53Updated this week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆66Updated 2 years ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆64Updated 3 weeks ago
• mit-crpg / OpenMOC
  A method of characteristics code for nuclear reactor physics calculations.
  ☆173Updated last year
• Ahmed-Naceur / dragon5
  Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code
  ☆11Updated 3 years ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆30Updated 6 months ago
• ezsolti / RFP
  ☆33Updated 5 months 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…
  ☆171Updated last week
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆40Updated 2 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆54Updated 2 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆122Updated this week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 6 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆34Updated this week
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆120Updated this week
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• weft / warp
  continuous energy monte carlo neutron transport in general geometries on GPUs
  ☆46Updated 8 years ago
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated last month
• pyne / pyne
  PyNE: The Nuclear Engineering Toolkit
  ☆306Updated 2 months ago
• mit-crpg / openmc-workshop
  Contains slides and example problems for OpenMC workshops and presentations
  ☆24Updated 3 years ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated last year
• Open-Sn / opensn
  Open-source Sn software
  ☆52Updated last week
• idaholab / virtual_test_bed
  The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
  ☆63Updated this week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆52Updated last week