Alternatives and similar repositories for mc-tools

Users that are interested in mc-tools are comparing it to the libraries listed below

• lanl / mcnptools
  ☆79Updated last year
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 3 years ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆46Updated this week
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last week
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆18Updated 4 months ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆42Updated 2 weeks ago
• alexhagen / wig
  a companion for writing MCNP input decks
  ☆12Updated 4 years ago
• abnowack / mcnpy
  Python Interface and Utility Functions for MCNP6
  ☆20Updated 8 years ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆37Updated last week
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆19Updated last year
• IAEA-NDS / open-benchmarks
  Computational inputs, reference outputs and experimental data for V&V systems
  ☆13Updated last month
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆29Updated 2 weeks ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆41Updated last week
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆58Updated 4 months ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆32Updated last week
• paulromano / endf-python
  Python ENDF Parser
  ☆33Updated 10 months ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated this week
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated last month
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆112Updated 3 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
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆33Updated 4 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆70Updated 3 weeks ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆26Updated last week
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated 3 weeks ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆29Updated this week
• svalinn / mcnp2cad
  Convert MCNP input files to a general CAD format
  ☆37Updated last year
• njoy / NJOY21
  NJOY for the 21st Century
  ☆79Updated last year
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆109Updated 2 weeks ago
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆28Updated last week
• sandialabs / MatMCNP
  A utility code for generating material cards for MCNP
  ☆21Updated 4 years ago