Alternatives and similar repositories for endf-python

Users that are interested in endf-python are comparing it to the libraries listed below

• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 3 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆28Updated 5 months ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated last week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆47Updated last month
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆63Updated last week
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last month
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆18Updated this week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆51Updated this week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated 11 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆80Updated 3 weeks ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated this week
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆33Updated last week
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆21Updated 2 years ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 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…
  ☆41Updated 10 months ago
• ezsolti / RFP
  ☆32Updated 3 months ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 5 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated last month
• AnderGray / openmc_uq_sinbad
  Repository for running SINBAD benchmarks with OpenMC and UQ
  ☆10Updated 3 years ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆82Updated last year
• fispact / pypact
  A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact
  ☆32Updated 3 months ago
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated 2 years ago
• 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
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated 3 weeks ago
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆22Updated 3 years ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆117Updated 2 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆48Updated last week
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year