Alternatives and similar repositories for mcnpy

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

• kbat / mc-tools
  Some Monte Carlo tools
  ☆53Updated 2 months ago
• sandialabs / MatMCNP
  A utility code for generating material cards for MCNP
  ☆23Updated 4 years 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.)
  ☆14Updated 13 years ago
• lanl / mcnptools
  ☆87Updated last year
• SAnsell / CombLayer
  MCNP(X) project builder using C++
  ☆17Updated last week
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆24Updated last year
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆22Updated 2 years ago
• murffer / MCNPTools
  Tools for usage with MCNP
  ☆10Updated 12 years ago
• svalinn / ALARA
  Simulation of transmutation and decay in nuclear systems
  ☆35Updated this week
• fusion-energy / magnetic_fusion_openmc_dagmc_paramak_example
  ☆17Updated last year
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆55Updated 4 months ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆53Updated 2 months ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆41Updated 2 weeks ago
• alexhagen / wig
  a companion for writing MCNP input decks
  ☆14Updated 4 years ago
• 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 8 years ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆52Updated last week
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆65Updated 2 weeks ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆35Updated 2 weeks ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆38Updated last month
• fusion-energy / openmc_source_plotter
  A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles
  ☆12Updated last year
• radioactivedecay / radioactivedecay
  A Python package for radioactive decay modelling that supports 1252 radionuclides, decay chains, branching, and metastable states.
  ☆111Updated 11 months ago
• inr-kit / numjuggler
  Tool to rename cells, surfaces, materials and universes in MCNP input files.
  ☆12Updated 3 years ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated 2 years ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆122Updated 11 months ago
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆38Updated 7 months ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year
• svalinn / mcnp2cad
  Convert MCNP input files to a general CAD format
  ☆38Updated 7 months ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 8 months ago
• mit-crpg / opendeplete
  A depletion framework for OpenMC
  ☆15Updated 8 years ago
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated 2 weeks ago