openmc-dev / openmc_mcnp_adapter

Related projects ⓘ

Alternatives and complementary repositories for openmc_mcnp_adapter

• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆21Updated 2 months ago
• paulromano / endf-python
  Python ENDF Parser
  ☆26Updated 3 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆57Updated last month
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆34Updated 3 weeks ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆12Updated 5 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆48Updated last month
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆32Updated this week
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆52Updated 5 months ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆14Updated 2 months ago
• eepeterson / openmc_fusion_benchmarks
  ☆17Updated 3 months ago
• lanl / mcnptools
  ☆67Updated 5 months ago
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 2 years ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆48Updated 3 weeks ago
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆35Updated last year
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆16Updated last year
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆25Updated 8 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆36Updated last month
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆25Updated 2 months ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆32Updated 3 years ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆23Updated this week
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆13Updated last month
• mctools / ncrystal
  NCrystal : a library for thermal neutron transport in crystals and other materials
  ☆41Updated this week
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆29Updated 8 months ago
• ukaea / SpaceClaim_API_NeutronicsTools
  Collection of tools for efficiency improvements in developing a CAD model for neutronics analysis
  ☆13Updated 3 years ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆73Updated 9 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆21Updated this 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…
  ☆38Updated last year
• ezsolti / RFP
  ☆29Updated last year
• stellarmesh / stellarmesh
  Meshing library for nuclear workflows
  ☆42Updated last month