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 3 years ago
• lanl / mcnptools
  ☆75Updated 8 months ago
• alexhagen / wig
  a companion for writing MCNP input decks
  ☆11Updated 3 years ago
• kbat / mc-tools
  Some Monte Carlo tools
  ☆47Updated 2 months ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆35Updated last week
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆36Updated last week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆37Updated last week
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆17Updated last year
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆60Updated this week
• SAnsell / CombLayer
  MCNP(X) project builder using C++
  ☆14Updated this week
• svanmaer / MCNPX_visualizer
  A visualizer based on POVRAY to create visualizations of MCNPX input files without the need for MCNPX (created by Nick Michiels.)
  ☆12Updated 12 years ago
• murffer / MCNPTools
  Tools for usage with MCNP
  ☆10Updated 11 years ago
• inr-kit / numjuggler
  Tool to rename cells, surfaces, materials and universes in MCNP input files.
  ☆11Updated 2 years ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated 3 weeks ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆30Updated 11 months ago
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆28Updated last month
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆50Updated last month
• svalinn / mcnp2cad
  Convert MCNP input files to a general CAD format
  ☆35Updated 10 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆27Updated 6 months ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 2 years ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• ukaea / SpaceClaim_API_NeutronicsTools
  Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis
  ☆13Updated 3 years ago
• radioactivedecay / radioactivedecay
  A Python package for radioactive decay modelling that supports 1252 radionuclides, decay chains, branching, and metastable states.
  ☆94Updated last week
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆26Updated 11 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆25Updated this week
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 5 months ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆29Updated last month
• mit-crpg / opendeplete
  A depletion framework for OpenMC
  ☆14Updated 7 years ago
• ukaea / neutronics_material_maker
  A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak
  ☆19Updated 3 years ago