Alternatives and similar repositories for mcnptools

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

• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆50Updated 3 weeks ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆48Updated this week
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated 2 weeks ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆29Updated 5 months ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated 11 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆64Updated last month
• IAEA-NDS / open-benchmarks
  Computational inputs, reference outputs and experimental data for V&V systems
  ☆15Updated 2 months ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆119Updated 2 months ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆118Updated 9 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆80Updated 3 weeks ago
• kbat / mc-tools
  Some Monte Carlo tools
  ☆52Updated last week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 5 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated 3 weeks ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated last year
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆51Updated 3 weeks ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆40Updated last month
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆23Updated 9 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated this week
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆18Updated last week
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆24Updated 6 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated last month
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 4 months ago
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆21Updated 2 years ago
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆35Updated this week
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆14Updated 6 months ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆17Updated 3 weeks ago
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆34Updated 4 months ago
• fusion-energy / neutronics-workshop
  A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…
  ☆168Updated this week
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆53Updated last month