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GitHub / fusion-energy / openmc_regular_mesh_plotter

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

JSON API: https://repos.ecosyste.ms/api/v1/hosts/GitHub/repositories/fusion-energy%2Fopenmc_regular_mesh_plotter

Stars: 7
Forks: 1
Open Issues: 7

License: mit
Language: Python
Repo Size: 181 KB
Dependencies: 10

Created: over 2 years ago
Updated: 23 days ago
Last pushed: 23 days ago
Last synced: 14 days ago

Topics: dose, map, mesh, neutronics, plot, regular, structured, tally

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