Alternatives and similar repositories for ENDFtk

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

• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆21Updated 2 years ago
• paulromano / endf-python
  Python ENDF Parser
  ☆38Updated last week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆47Updated last month
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated 3 weeks ago
• njoy / ACEtk
  Toolkit for working with ACE-formatted data files
  ☆30Updated last month
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆28Updated 5 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆63Updated last week
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 3 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆80Updated 3 weeks ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆33Updated last week
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆16Updated 6 months ago
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆22Updated 3 years ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated last week
• njoy / NJOY21
  NJOY for the 21st Century
  ☆82Updated last year
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last month
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆31Updated last week
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆116Updated 8 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆117Updated 2 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆48Updated last week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated 11 months ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆20Updated 9 months ago
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆18Updated this week
• lanl / mcnptools
  ☆85Updated last year
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆14Updated 5 months ago
• fispact / pypact
  A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact
  ☆32Updated 3 months ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 5 months ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 3 years ago
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆34Updated 3 months ago