fusion-energy / openmc_source_plotter

Related projects ⓘ

Alternatives and complementary repositories for openmc_source_plotter

• fusion-energy / magnetic_fusion_openmc_dagmc_paramak_example
  ☆12Updated 7 months ago
• IAEA-NDS / PREPRO
  ENDF/B pre-processing codes (PREPRO)
  ☆16Updated last year
• openmc-dev / openmc-ecosystem
  List of open source projects related to OpenMC
  ☆21Updated 2 months ago
• ahmedkmadani / OpenMCProject
  Simulate PWR,CANDU and VVER reactor (Assembly Model) using OpenMC https://openmc.readthedocs.io/en/stable/
  ☆11Updated 4 years ago
• fusion-energy / neutronics_material_maker
  A tool for making reproducible materials and standardizing use across several neutronics codes
  ☆20Updated last month
• fusion-energy / openmc-plasma-source
  Creates a plasma source as an openmc.source object from input parameters that describe the plasma
  ☆28Updated this week
• openmc-dev / openmc_mcnp_adapter
  Tool for converting MCNP input files to OpenMC classes/XML
  ☆36Updated 3 weeks ago
• eepeterson / openmc_fusion_benchmarks
  ☆17Updated 3 months ago
• njoy / ENDFtk
  Toolkit for reading and interacting with ENDF-6 formatted files
  ☆34Updated 3 weeks ago
• paulromano / endf-python
  Python ENDF Parser
  ☆26Updated 3 months ago
• fusion-energy / fusion_neutronics_workflow
  Combines open source packages to produce an automated fusion specific neutronics workflow
  ☆14Updated 2 years ago
• lanl / TOGA
  Tool for Optimization and Group-structure Analysis of nuclear multi-group cross sections
  ☆10Updated 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
• ukaea / openmc_workshop
  A selection of resources for learning openmc with particular focus on simulations relevant for fusion energy
  ☆39Updated 3 years ago
• watts-dev / watts
  Workflow and Template Toolkit for Simulation (WATTS)
  ☆25Updated 2 months ago
• openmc-dev / openmc-notebooks
  Example Jupyter notebooks for OpenMC
  ☆30Updated 4 months ago
• luca-fiorito-11 / sandy
  Sampling nuclear data and uncertainty
  ☆48Updated last month
• openmc-dev / data
  Collection of scripts for managing data for OpenMC
  ☆28Updated 11 months ago
• stellarmesh / stellarmesh
  Meshing library for nuclear workflows
  ☆42Updated last month
• openmc-data-storage / openmc_data_downloader
  A Python package for downloading h5 cross section files for use in OpenMC.
  ☆11Updated last year
• openmc-dev / plotter
  Native plotting GUI for model design and verification
  ☆48Updated 3 weeks ago
• GEOUNED-org / GEOUNED
  A tool to convert CAD to CSG & CSG to CAD for Monte Carlo transport codes
  ☆57Updated last month
• openmsr / CAD_to_OpenMC
  code to target the conversion from a step-file to a h5m-geometry for neutronics
  ☆29Updated last month
• 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
• svalinn / parastell
  Parametric 3-D CAD modeling toolset for stellarator fusion devices
  ☆26Updated this week
• alexhagen / wig
  a companion for writing MCNP input decks
  ☆11Updated 3 years ago
• aurora-multiphysics / aurora
  Aurora is A Unified Resource for OpenMC (fusion) Reactor Applications.
  ☆36Updated 4 months ago
• idaholab / MontePy
  MontePy is the most user friendly Python library (API) to read, edit, and write MCNP input files.
  ☆32Updated this week
• fispact / pypact
  A Python package for parsing FISPACT-II output
  ☆25Updated 8 months ago
• jlball / arc-nonproliferation
  An OpenMC-based repo for studying proliferation issues in ARC-class fusion reactors.
  ☆11Updated 2 months ago