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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Adding energy filter num_dims check to avoid crash #64

Closed shimwell closed 7 months ago

shimwell commented 7 months ago

As discussed here https://openmc.discourse.group/t/neutron-flux-in-a-graphite-stack/3916/15

A tally with an energy filter has multiple values and there is not arg to indicate which one to plot. So for now we can check for the existance of energy filters that have more than 1 num_dims and raise a value error with a clear message to the user.