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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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Fix flipped data #27

Closed RemDelaporteMathurin closed 2 years ago

RemDelaporteMathurin commented 2 years ago

This PR fixes the flipping of the y data due to imshow default behaviour of putting the origin at the top

shimwell commented 2 years ago

Thanks Remi