Alternatives and similar repositories for FESTIM-workshop:

Users that are interested in FESTIM-workshop are comparing it to the libraries listed below

• RemDelaporteMathurin / h-transport-materials
  Easily access hydrogen transport properties
  ☆15Updated 3 months ago
• festim-dev / FESTIM
  Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS
  ☆100Updated this week
• eepeterson / openmc_fusion_benchmarks
  ☆18Updated this week
• ERMETE-Lab / MP-OFELIA
  Openmc-FEnicsx for muLtiphysics tutorIAl
  ☆14Updated 7 months 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
• jlball / arc-nonproliferation
  An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.
  ☆11Updated 6 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
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated last month
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆24Updated 6 months ago
• Open-Sn / opensn
  open-source Sn software
  ☆27Updated this week
• paulromano / endf-python
  Python ENDF Parser
  ☆31Updated 7 months ago
• ukaea / PROCESS
  PROCESS is a systems code at UKAEA that calculates in a self-consistent manner the parameters of a fusion power plant with a specified pe…
  ☆43Updated this week
• ezsolti / RFP
  ☆30Updated last month
• aprilnovak / Okapi
  OpenMC wrapped as a Moose App
  ☆16Updated last year
• openmc-dev / openmc_cad_adapter
  Convert OpenMC Geometry Components to CAD
  ☆17Updated 4 months ago
• openmc-data-storage / openmc_data_downloader
  A Python package for downloading h5 cross section files for use in OpenMC.
  ☆12Updated 2 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 10 months ago
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆33Updated 3 months ago
• openmc-data-storage / isotope-xs-plotter
  XSPlot - Neutron cross section plotter for isotopes
  ☆14Updated last year
• fusion-energy / magnetic_fusion_openmc_dagmc_paramak_example
  ☆14Updated 11 months ago
• IRFM / divHretention
  Tool to estimate H retention in tokamak divertors
  ☆10Updated 3 years ago
• elementx54 / moosefw_vim
  Vim plugin for MOOSE Framework input file format
  ☆12Updated last year
• fusion-energy / fusion_neutronics_workflow
  Combines open source packages to produce an automated fusion specific neutronics workflow
  ☆14Updated 2 years ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆40Updated 9 months ago
• dassh-dev / dassh
  Ducted Assembly Steady State Heat Transfer Software (DASSH)
  ☆17Updated last year
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆39Updated last month
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆56Updated 2 months ago
• landreman / sfincs
  SFINCS: the Stellarator Fokker-Planck Iterative Neoclassical Conservative Solver
  ☆25Updated 2 months ago
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆25Updated this week
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆10Updated 2 years ago