Alternatives and similar repositories for openmc_data_downloader

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

• jlball / arc-nonproliferation
  An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.
  ☆11Updated last year
• eepeterson / openmc_fusion_benchmarks
  Automated V&V for fusion relevant CAD-based benchmarks
  ☆23Updated 3 months ago
• AnderGray / openmc_uq_sinbad
  Repository for running SINBAD benchmarks with OpenMC and UQ
  ☆10Updated 3 years ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆11Updated 3 years ago
• svalinn / pydagmc
  A convenience interface for examining and reassigning metadata in DAGMC models with PyMOAB
  ☆16Updated last week
• openmc-data-storage / isotope-xs-plotter
  XSPlot - Neutron cross section plotter for isotopes
  ☆14Updated 2 years ago
• IRFM / divHretention
  Tool to estimate H retention in tokamak divertors
  ☆10Updated 4 years ago
• LLNL / fudge
  For Updating Data and Generating Evaluations (FUDGE): LLNL code for managing nuclear data
  ☆31Updated this week
• ukaea / neutronics_material_maker
  A tool for making parametric material cards for use in neutronics codes. Original developed for the Paramak
  ☆19Updated 4 years ago
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆41Updated 4 years ago
• RemDelaporteMathurin / fusion-world
  ☆17Updated 3 years ago
• paulromano / endf-python
  Python ENDF Parser
  ☆38Updated this week
• xdg-org / xdg
  Accelerated Discretized Geometry
  ☆18Updated this week
• JADE-V-V / JADE
  JADE, a novel nuclear data libraries V&V tool
  ☆33Updated last week
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆38Updated 4 months ago
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆28Updated 4 months ago
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆47Updated last month
• fispact / pypact
  A Python package for parsing FISPACT-II output. https://deepwiki.com/fispact/pypact
  ☆32Updated 2 months ago
• fusion-energy / magnetic_fusion_openmc_dagmc_paramak_example
  ☆16Updated last year
• svalinn / parastell
  Parametric 3-D modeling toolset for stellarator fusion devices
  ☆36Updated 2 weeks ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆52Updated 3 weeks ago
• fusion-energy / openmc_regular_mesh_plotter
  A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
  ☆14Updated 5 months ago
• festim-dev / FESTIM
  Coupled hydrogen/tritium transport and heat transfer modelling using FEniCS
  ☆113Updated this week
• toshihikokawano / DeCE
  ENDF-6 data interface and nuclear data evaluation assist code
  ☆16Updated 5 months ago
• Fusion4Energy / F4Enix
  API for parsing and post-processing many MC simulations related files
  ☆17Updated last month
• fusion-energy / plasmaboundaries
  Determine plasma flux functions for various plasma parameters and plasma configurations.
  ☆13Updated 3 years ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆43Updated last year
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆63Updated last week
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆34Updated 3 months ago
• ezsolti / RFP
  ☆32Updated 3 months ago