Alternatives and similar repositories for magnetic_fusion_openmc_dagmc_paramak_example:

Users that are interested in magnetic_fusion_openmc_dagmc_paramak_example are comparing it to the libraries listed below

• fusion-energy / openmc_source_plotter
  A Python package for extracting and plotting the locations, directions, energy distributions of OpenMC source particles
  ☆10Updated 8 months ago
• openmc-data-storage / openmc_data_downloader
  A Python package for downloading h5 cross section files for use in OpenMC.
  ☆11Updated last week
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆16Updated last year
• eepeterson / openmc_fusion_benchmarks
  ☆18Updated 5 months ago
• jlball / arc-nonproliferation
  An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.
  ☆11Updated 4 months ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆10Updated 2 years ago
• openmc-data-storage / isotope-xs-plotter
  XSPlot - Neutron cross section plotter for isotopes
  ☆14Updated last year
• 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
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆31Updated last month
• 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
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• IRFM / divHretention
  Tool to estimate H retention in tokamak divertors
  ☆10Updated 3 years ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆22Updated 4 months ago
• RemDelaporteMathurin / h-transport-materials
  Easily access hydrogen transport properties
  ☆15Updated 3 weeks ago
• paulromano / endf-python
  Python ENDF Parser
  ☆27Updated 5 months ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆35Updated 2 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆49Updated last week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆37Updated 3 weeks ago
• svalinn / Cubit-plugin
  Plugins and command extensions for Coreform Cubit
  ☆18Updated 7 months ago
• festim-dev / FESTIM-workshop
  Learn how to simulate hydrogen transport with FESTIM
  ☆18Updated 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 8 months ago
• festim-dev / FESTIM
  Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS
  ☆97Updated this week
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆25Updated 4 months ago
• exasmr / openmc
  OpenMC Monte Carlo Code
  ☆17Updated 4 months ago
• fusion-energy / fusion_neutronics_workflow
  Combines open source packages to produce an automated fusion specific neutronics workflow
  ☆14Updated 2 years ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆13Updated 7 months ago
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆54Updated last month
• fusion-energy / plasmaboundaries
  Determine plasma flux functions for various plasma parameters and plasma configurations.
  ☆11Updated 2 years ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆34Updated this week
• svalinn / parastell
  Parametric 3-D CAD modeling toolset for stellarator fusion devices
  ☆27Updated this week