Alternatives and similar repositories for openmc-plasma-source

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

• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆24Updated 9 months ago
• svalinn / parastell
  Parametric 3-D CAD modeling toolset for stellarator fusion devices
  ☆32Updated this week
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆32Updated 2 weeks ago
• fusion-energy / paramak
  Create parametric 3D fusion reactor CAD and neutronics models
  ☆86Updated 3 months ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆41Updated last year
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 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
• 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
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆59Updated 5 months ago
• stellarmesh / stellarmesh
  Meshing library for nuclear workflows
  ☆51Updated 3 months ago
• 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…
  ☆155Updated last week
• paulromano / endf-python
  Python ENDF Parser
  ☆34Updated 11 months ago
• svalinn / DAGMC
  Direct Accelerated Geometry Monte Carlo Toolkit
  ☆112Updated 5 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆31Updated last month
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆26Updated last month
• Open-Sn / opensn
  open-source Sn software
  ☆36Updated this week
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated last week
• enrico-dev / enrico
  ENRICO: Exascale Nuclear Reactor Investigative COde
  ☆65Updated last year
• CambridgeNuclear / SCONE
  Stochastic Calculator Of Neutron transport Equation
  ☆45Updated last week
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆71Updated 3 weeks ago
• pshriwise / xdg
  Accelerated Discretized Geometry
  ☆17Updated last week
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated 3 weeks ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 2 years ago
• ukaea / neutronics_material_maker
  A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak
  ☆19Updated 3 years ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆32Updated 3 weeks ago
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆33Updated 6 months ago
• fusion-energy / fusion_neutronics_workflow
  Combines open source packages to produce an automated fusion specific neutronics workflow
  ☆15Updated 3 years ago
• fusion-energy / cad_to_h5m
  Converts CAD file(s) such as STP and SAT to a h5m file compatible with DAGMC based simulations using the Cubit Python API
  ☆12Updated last year
• makeclean / csg2csg
  Tools to translate between different CSG geometry types
  ☆39Updated last month
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆47Updated this week