Alternatives and similar repositories for ACEtk:

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

• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆39Updated last week
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆18Updated last year
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated last week
• paulromano / endf-python
  Python ENDF Parser
  ☆31Updated 8 months ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆40Updated last month
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆25Updated this week
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated 2 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆30Updated this week
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆42Updated 2 months ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated 2 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 7 months ago
• eepeterson / openmc_fusion_benchmarks
  ☆19Updated last 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…
  ☆39Updated 3 months ago
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆28Updated last year
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆30Updated 2 months ago
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆21Updated 2 years ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆63Updated this week
• HunterBelanger / papillon-ndl
  Papillon Nuclear Data Library
  ☆14Updated 7 months ago
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆29Updated 2 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆56Updated last month
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 2 years ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆17Updated 4 months ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆78Updated last year
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆16Updated this week
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆11Updated 10 months ago
• mctools / ncrystal
  NCrystal : a library for thermal neutron transport in crystals and other materials
  ☆44Updated this week
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆13Updated this week