Alternatives and similar repositories for vscode_mcnp

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

• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆49Updated this week
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆10Updated 3 years ago
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated 3 weeks ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆84Updated last month
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆52Updated last month
• lanl / mcnptools
  ☆87Updated last year
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆30Updated 7 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 3 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆39Updated 2 months ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated last week
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆18Updated last month
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆53Updated 3 weeks ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆20Updated last year
• alexhagen / wig
  a companion for writing MCNP input decks
  ☆12Updated 4 years ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆123Updated 3 weeks ago
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆22Updated last month
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆40Updated 7 months ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆23Updated 11 months ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆40Updated 2 weeks ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆84Updated last year
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆34Updated 3 weeks ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆54Updated 3 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 8 months 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 3 months ago
• fispact / pypact
  A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact
  ☆33Updated last month
• kbat / mc-tools
  Some Monte Carlo tools
  ☆52Updated last month
• IAEA-NDS / endf-parserpy
  Python package for reading, writing, verifying and translating ENDF-6 formatted files
  ☆23Updated 5 months ago