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
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆52Updated last week
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated last month
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆53Updated 2 months ago
• njoy / ACEtk
  Toolkit for working with ACE-formatted data files
  ☆30Updated 3 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆64Updated 2 weeks ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆30Updated 6 months ago
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆32Updated last month
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆118Updated 9 months ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated last year
• lanl / mcnptools
  ☆87Updated last year
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated this week
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆121Updated 3 months ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆23Updated 10 months ago
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆19Updated last week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆81Updated last week
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆16Updated 7 months ago
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last month
• Open-Sn / opensn
  Open-source Sn software
  ☆52Updated this week
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆17Updated this week
• AnderGray / openmc_uq_sinbad
  Repository for running SINBAD benchmarks with OpenMC and UQ
  ☆10Updated 3 years ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 6 months ago
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆22Updated 3 years ago
• 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…
  ☆42Updated last year
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 3 years ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆34Updated this week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆38Updated last week