openmc-dev/openmc-ecosystem

List of open source projects related to OpenMC

OpenMC Ecosystem

A list of open source projects related to the OpenMC Monte Carlo particle transport framework.

Visualization

• OpenMC Plotter — Official geometry/tally visualization GUI

Multiphysics and Coupling

• ARMI-OpenMC Plugin — OpenMC plugin for ARMI
• Aurora — OpenMC wrapped as a MOOSE app
• Cardinal — OpenMC and nekRS wrapped as MOOSE apps
• ENRICO — Monte Carlo + CFD coupling application
• ONIX — Python-based burnup code
• WATTS — Python-based tool for templated simulations

Geometry Conversion

• csg2csg — Tool to translate between different CSG types
• openmc_mcnp_adapter — Tool for converting MCNP to OpenMC

CAD Ecosystem

• CAD_to_DAGMC — Convert CAD geometry to DAGMC h5m files
• CAD_to_OpenMC — Convert STEP files to DAMC h5m files
• DAGMC — Direct accelerated geometry Monte Carlo toolkit
• GEOUNED — Tool that converts CAD to CSG and vice versa
• Paramak — Parametric 3D fusion reactor CAD and neutronics models
• StellarMesh — DAGMC geometry creator

Nuclear Data

• data scripts — Scripts used to produce OpenMC nuclear data libraries
• FrendyPlus — Data processing code built on top of Frendy that can generate HDF5 libraries for OpenMC

Models and Validation

• benchmarks — Reactor physics benchmark models
• MSRE — Detailed CAD model of the MSRE
• validation scripts — Scripts used to automate V&V activities
• JADE — Automated framework for V&V of nuclear data and transport codes
• open_fusion_benchmarks — Automated framework for comparing OpenMC to fusion integral benchmarks

Convenience Tools

• MCPL — Tool for manipulating phase-space source files and passing between Monte Carlo codes
• neutronics_material_maker — Make reproducible materials and standardize across codes
• openmc_cell_segmenter — Segment OpenMC cells into smaller cells
• openmc-plasma-source — Create a plasma source from input parameters
• ParaStell — Parametric 3D CAD modeling tool for stellarators
• PyNE — Nuclear engieering toolkit to assist with modeling and simulation
• TOGA — Multigroup cross section generation with optimization/analysis

Training resources

• neutronics-workshop — Jupyter notebook based training course for fusion neutronics

openmc-ecosystem's Issues

ONIX

May we can add ONIX by @jlanversin to the list.