Alternatives and similar repositories for MatMCNP:

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

• abnowack / mcnpy
  Python Interface and Utility Functions for MCNP6
  ☆20Updated 8 years ago
• alexhagen / wig
  a companion for writing MCNP input decks
  ☆12Updated 4 years ago
• kbat / mc-tools
  Some Monte Carlo tools
  ☆48Updated last month
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆43Updated this week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆40Updated 2 months ago
• lanl / mcnptools
  ☆77Updated 11 months ago
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 3 years ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated 3 months ago
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆19Updated last year
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated this week
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆25Updated 8 months ago
• svanmaer / MCNPX_visualizer
  A visualizer based on POVRAY to create visualizations of MCNPX input files without the need for MCNPX (created by Nick Michiels.)
  ☆13Updated 12 years ago
• SAnsell / CombLayer
  MCNP(X) project builder using C++
  ☆15Updated this week
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆15Updated 2 weeks ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆30Updated this week
• inr-kit / numjuggler
  Tool to rename cells, surfaces, materials and universes in MCNP input files.
  ☆11Updated 2 years ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆31Updated 3 months ago
• repositony / vscode_mcnp
  MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks.
  ☆12Updated 10 months ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated this week
• EL-Bakkali-Jaafar / ERSN-OpenMC
  ERSN-OpenMC is a Graphical User Interface for OpenMC Monte Carlo particle transport simulation code, originally developed by Jaafar EL Ba…
  ☆13Updated 7 years ago
• paulromano / endf-python
  Python ENDF Parser
  ☆33Updated 9 months ago
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆29Updated 2 weeks ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆37Updated last year
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆28Updated 2 weeks ago
• eepeterson / openmc_fusion_benchmarks
  ☆22Updated this week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• svalinn / ALARA
  Simulation of transmutation and decay in nuclear systems
  ☆28Updated 3 months ago
• fusion-energy / magnetic_fusion_openmc_dagmc_paramak_example
  ☆15Updated last year
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆57Updated 3 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆69Updated 3 weeks ago