A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
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Updated
Oct 19, 2024 - Jupyter Notebook
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
Meshing library for nuclear workflows
Package Manager for Nuclear Engineering Development
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
A Python package that extends OpenMC base classes to provide convenience features and standardized tallies when simulating DAGMC geometry with OpenMC.
Converts mesh vertices and connectivity to h5m geometry files compatible with DAGMC simulations
A minimal example implementation of an open source method of making DAGMC geometry with Paramak and simulating tritium production with OpenMC
Combines open source packages to produce an automated fusion specific neutronics workflow
The same neutronics geometry made using Constructive Solid Geometry (CSG) and DAGMC faceteted surface mesh at different resolutions to compare simulation results
Visualization tools and tricks for DAGMC problems
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