Perform a set of standard neutronics simulations with OpenMC and DAGMC
Project description
OpenMC DAGMC Wrapper
The openmc-dagmc-wrapper python package extends OpenMC base classes and adds convenience features aimed as easing the use of OpenMC with DAGMC for fixed-source simulations.
The openmc-dagmc-wrapper is built around the assumption that a DAGMC geometry in the form of a h5m is used as the simulation geometry. This allows several aspects of openmc simulations to be simplified and automated.
Additional convenience is available when making tallies as standard tally types are added which automated the application of openmc.Filters and openmc.scores for standard tallies such as neutron spectra, effective dose, heating, TBR and others.
Further simplifications are access by using additional packages from the fusion-neutronics-workflow
If you are looking for an easy neutronics interface for performing simulations of fusion reactors this package was built for you.
:point_right: Documentation
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:point_right: Installation
:point_right: Examples
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