Alternatives and similar repositories for mcnpy

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

• sandialabs / MatMCNP
  A utility code for generating material cards for MCNP
  ☆21Updated 4 years ago
• kbat / mc-tools
  Some Monte Carlo tools
  ☆50Updated 3 weeks ago
• lanl / mcnptools
  ☆83Updated last year
• 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
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆18Updated 6 months ago
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆19Updated last year
• svalinn / ALARA
  Simulation of transmutation and decay in nuclear systems
  ☆29Updated 6 months ago
• SAnsell / CombLayer
  MCNP(X) project builder using C++
  ☆15Updated 3 weeks ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated this week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆44Updated 2 months ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆32Updated this week
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆60Updated 6 months ago
• radioactivedecay / radioactivedecay
  A Python package for radioactive decay modelling that supports 1252 radionuclides, decay chains, branching, and metastable states.
  ☆100Updated 5 months ago
• murffer / MCNPTools
  Tools for usage with MCNP
  ☆10Updated 11 years ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated last month
• svalinn / mcnp2cad
  Convert MCNP input files to a general CAD format
  ☆37Updated last month
• alexhagen / wig
  a companion for writing MCNP input decks
  ☆12Updated 4 years ago
• fusion-energy / openmc_source_plotter
  A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles
  ☆10Updated last year
• fusion-energy / magnetic_fusion_openmc_dagmc_paramak_example
  ☆16Updated last year
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated this week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆72Updated last month
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆112Updated 5 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆34Updated last year
• mctools / ncrystal
  NCrystal : a library for thermal neutron transport in crystals and other materials
  ☆46Updated this week
• inr-kit / numjuggler
  Tool to rename cells, surfaces, materials and universes in MCNP input files.
  ☆12Updated 2 years ago
• fispact / pypact
  A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact
  ☆29Updated last week
• njoy / NJOY21
  NJOY for the 21st Century
  ☆79Updated last year
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated 3 weeks ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 2 years ago