Alternatives and similar repositories for data

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

• openmc-dev / validation
  Collection of validation scripts, notebooks, results
  ☆11Updated last year
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆60Updated last week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated 2 weeks ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆48Updated last week
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆18Updated 6 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆35Updated 2 weeks ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆114Updated 6 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆27Updated 2 months ago
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆66Updated 2 years ago
• Open-Sn / opensn
  open-source Sn software
  ☆39Updated this week
• CEMeNT-PSAAP / MCDC
  MC/DC: Monte Carlo Dynamic Code
  ☆43Updated this week
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆21Updated 2 years ago
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated 2 years ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆44Updated 3 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆32Updated 2 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆115Updated 2 weeks ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 4 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 2 years ago
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆54Updated 10 months ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆32Updated 2 months ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated last month
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• 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 8 months ago
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆30Updated last month
• njoy / NJOY21
  NJOY for the 21st Century
  ☆80Updated last year
• 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…
  ☆158Updated last week
• Ahmed-Naceur / dragon5
  Three-Dimensional Discrete Ordinates Neutron, Photon, Electron and Positron Transport Code
  ☆10Updated 3 years ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated this week