Alternatives and similar repositories for MontePy

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

• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last week
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆31Updated 8 months ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆53Updated last month
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 3 weeks ago
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated last week
• IAEA-NDS / open-benchmarks
  Computational inputs, reference outputs and experimental data for V&V systems
  ☆15Updated 4 months ago
• lanl / mcnptools
  ☆87Updated last year
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆85Updated 2 months ago
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆23Updated 3 weeks ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆64Updated last week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆18Updated last month
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 8 months ago
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆14Updated 9 months ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated 2 years ago
• AnderGray / openmc_uq_sinbad
  Repository for running SINBAD benchmarks with OpenMC and UQ
  ☆10Updated 3 years ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆61Updated 4 months ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 3 years ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆33Updated 7 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆34Updated 3 weeks ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆55Updated 2 weeks ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆24Updated last year
• ezsolti / RFP
  ☆33Updated 6 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
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆120Updated 11 months ago
• repositony / vscode_mcnp
  MCNP6 Syntax highlighting and code snippets for VSCode. Written primarily for MCNP6.x input decks as a placeholder for the full LSP is im…
  ☆15Updated last year
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆55Updated 4 months ago
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆25Updated last year
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆24Updated 3 weeks ago