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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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Move the mesh data from 0,0 #2

Closed shimwell closed 3 years ago

shimwell commented 3 years ago

This link shows how to move the data https://moonbooks.org/Articles/How-to-change-imshow-axis-values-labels-in-matplotlib-/

This will help line up the mesh with the geometry

shimwell commented 3 years ago

It might be required to get the extent from the openm mesh filter

# MeshFilter
mesh = my_tally.filters[2]
mesh.mesh.lower_left
mesh.mesh.upper_right
shimwell commented 3 years ago

solved