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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added requested_units to functions #12

Closed shimwell closed 3 years ago

shimwell commented 3 years ago

Added the ability to propagate unit conversion through the functions and added dose plotting functions

shimwell commented 3 years ago

tests pass locally