allowing multiple tallies to be added and plotted

fusion-energy / openmc_regular_mesh_plotter

A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.

MIT License

9 stars 1 forks source link

allowing multiple tallies to be added and plotted #62

Closed shimwell closed 10 months ago

shimwell commented 10 months ago

this PR allows one to pass in a list of tallies and have the results added.

this is useful for tallying photon and neutron dose separately as they have different coefficients and then adding the two on a single plot as they combine to give dose in Sv

I have added a new example to the examples folder