Alternatives and similar repositories for NE250:

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

• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆57Updated 3 months ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆31Updated 3 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆106Updated last week
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆52Updated 6 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆57Updated last week
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆112Updated 2 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆42Updated last week
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆25Updated 7 months ago
• eepeterson / openmc_fusion_benchmarks
  ☆21Updated 2 weeks ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆33Updated 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
• idaholab / virtual_test_bed
  The National Reactor Innovation Center's (NRIC) Virtual Test Bed Repository
  ☆53Updated this week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆65Updated last year
• ezsolti / RFP
  ☆30Updated 2 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆69Updated 2 weeks ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆40Updated 2 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆33Updated 8 months ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆41Updated last week
• njoy / NJOY21
  NJOY for the 21st Century
  ☆78Updated last year
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆37Updated last year
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆15Updated this week
• lanl / mcnptools
  ☆77Updated 10 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆40Updated 10 months ago
• openmsr / msr-archive
  curated documents pertaining to early molten salt reactor research.
  ☆22Updated last year
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆28Updated this week
• paulromano / cnl-workshop
  OpenMC Workshop for Canadian Nuclear Laboratories
  ☆10Updated 8 years ago
• neams-th-coe / cardinal
  High-Fidelity Multiphysics
  ☆106Updated this week
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆24Updated 6 months ago
• mohamedlahdour / OpenNTP
  In this project we develop an OpenNTP package to solve the multi-group neutron transport equation.
  ☆11Updated 4 years ago
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 2 years ago