Alternatives and similar repositories for openmc-notebooks:

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

• fusion-energy / neutronics-workshop
  A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutroni…
  ☆135Updated this week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆60Updated 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
• mit-crpg / openmc-workshop
  Contains slides and example problems for OpenMC workshops and presentations
  ☆23Updated 2 years ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆55Updated 3 weeks ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆37Updated this week
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 5 months ago
• lanl / mcnptools
  ☆75Updated 8 months ago
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆39Updated 3 weeks ago
• mit-crpg / BEAVRS
  A two-cycle full-core PWR depletion benchmark based on a commercial nuclear power plant
  ☆33Updated last month
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆36Updated last week
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆108Updated this week
• njoy / NJOY2016
  Nuclear data processing with legacy NJOY
  ☆102Updated 2 weeks ago
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆32Updated 3 weeks ago
• paulromano / endf-python
  Python ENDF Parser
  ☆27Updated 6 months ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆29Updated last month
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆36Updated last year
• CORE-GATECH-GROUP / serpent-tools
  A suite of parsers designed to make interacting with SERPENT output files simple and flawless
  ☆55Updated last week
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆23Updated 4 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆50Updated last month
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆14Updated 2 weeks ago
• njoy / NJOY21
  NJOY for the 21st Century
  ☆77Updated last year
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆25Updated 5 months ago
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆17Updated last year
• mctools / mcpl
  Monte Carlo Particle Lists
  ☆30Updated 11 months ago
• mit-crpg / benchmarks
  Collection of models for reactor physics benchmarks
  ☆50Updated 4 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 9 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆40Updated 7 months ago
• highness-eu / NJOY-NCrystal-Library
  Thermal Scattering Library created with NJOY+NCrystal
  ☆9Updated 2 years ago
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆32Updated 2 months ago