Alternatives and similar repositories for openmc-reactor-examples

Users that are interested in openmc-reactor-examples are comparing it to the libraries listed below

• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆36Updated 3 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆26Updated 3 weeks ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆59Updated 5 months ago
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆18Updated 7 months ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 2 weeks ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆42Updated last month
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last week
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆38Updated 3 weeks ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆44Updated 2 weeks ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆29Updated 3 weeks ago
• paulromano / endf-python
  Python ENDF Parser
  ☆33Updated 10 months ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated last month
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆47Updated 2 weeks ago
• IAEA-NDS / open-benchmarks
  Computational inputs, reference outputs and experimental data for V&V systems
  ☆13Updated 2 months ago
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆58Updated 2 months ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆70Updated last month
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆11Updated last month
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆17Updated last week
• openmsr / msr-archive
  curated documents pertaining to early molten salt reactor research.
  ☆22Updated last year
• 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 6 months ago
• mit-crpg / openmc-workshop
  Contains slides and example problems for OpenMC workshops and presentations
  ☆23Updated 3 years ago
• NuclearData / ACEFormat
  Format description for ACE nuclear data files
  ☆21Updated 3 years ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆41Updated 2 weeks ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆51Updated last week
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated 2 years ago
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆110Updated last month
• KDSource / KDSource
  Tool for modeling distributional particle sources for Monte Carlo simulations, with Kernel Density Estimation.
  ☆22Updated last month
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆24Updated 8 months ago
• ezsolti / RFP
  ☆31Updated last week