Alternatives and similar repositories for NJOY-NCrystal-Library

Users that are interested in NJOY-NCrystal-Library are comparing it to the libraries listed below

• 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
  ☆71Updated 3 weeks 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…
  ☆13Updated last year
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆43Updated last month
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆26Updated last month
• paulromano / endf-python
  Python ENDF Parser
  ☆34Updated 11 months ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆47Updated this week
• IAEA-NDS / open-benchmarks
  Computational inputs, reference outputs and experimental data for V&V systems
  ☆13Updated 3 months ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated this week
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆18Updated 7 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆59Updated 5 months ago
• lanl / mcnptools
  ☆82Updated last year
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆17Updated last week
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆38Updated last week
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated last week
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆111Updated last month
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆39Updated last month
• njoy / NJOY21
  NJOY for the 21st Century
  ☆79Updated last year
• IAEA-NDS / endf-parserpy
  Python package for reading, writing, verifying and translating ENDF-6 formatted files
  ☆18Updated this week
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆31Updated last month
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆45Updated last week
• jlanversin / ONIX
  ONIX is an open-source depletion software for nuclear reactor simulations and nuclear archaeology. It is written in Python 3 and offers c…
  ☆40Updated 7 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆59Updated 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.
  ☆11Updated 2 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated 3 weeks ago
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆22Updated 2 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆36Updated this week
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆29Updated last month
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆40Updated last week