A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools

Create parametric 3D fusion reactor CAD and neutronics models

Meshing library for nuclear workflows

Convert CAD geometry (STP files) or Cadquery assemblies to DAGMC h5m files

Combines open source packages to produce an automated fusion specific neutronics workflow

Package Manager for Nuclear Engineering Development

A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.

A minimal example implementation of an open source method of making DAGMC geometry with Paramak and simulating tritium production with OpenMC

Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations

Convert non overlapping STL files into a DAGMC h5m file complete with material tags and ready for use in neutronics simulations.

Visualization tools and tricks for DAGMC problems

A Python package to identify the part ID number in Brep format CAD files

Finds the bounding box and related properties of a DAGMC geometry

The same neutronics geometry made using Constructive Solid Geometry (CSG) and DAGMC faceteted surface mesh at different resolutions to compare simulation results

Radiation transport simulations with a human phantoms in OpenMC. Meshes are created in Cubit Coreform. The phantom used in this project is obtained from: https://www.icrp.org/publication.asp?id=ICRP%20Publication%20145