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Perform a set of standard neutronics simulations with OpenMC and DAGMC

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OpenMC DAGMC Wrapper

The openmc-dagmc-wrapper python package allows convenient access to a series of standard neutronics simulations and post using OpenMC and DAGMC.

The intended use case is to take DAGMC compatible h5m files generated by cad_to_h5m with CAD file inputs from the Paramak as demonstrated in the neutronics_workflow. However the package can also be used with h5m files generated in other ways.

Standard simulations tallies are facilitated:

  • Volume / cell tallies
  • Regular 2D mesh tallies
  • Regular 3D mesh tallies
  • Unstructured mesh tally (on road map)

Neutronics responses can be obtained:

  • Tritium Breeding Ratio (TBR)
  • Heating (photon and neutron)
  • Dose (on road map)
  • Any supported reaction from the standard OpenMC reactions

A standard collection of materials are available by making use of the neutronics_material_maker package.

OpenMC sources definitions are used for the particle sources.

Post processing of results are also carried out to automatically provide images, JSON output files and VTK files for convenient access to the results.

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:point_right: Examples

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