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fusion-energy / openmc_regular_mesh_plotter

A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
MIT License
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Accepting tally inputs #5

Closed shimwell closed 2 years ago

shimwell commented 2 years ago

this PR adds the option of plotting meshes from the openmc tally object.

This has the advantage of no longer requiring the user to specify extent as it can be worked out from the tally.filter.MeshFilter object