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openmc_regular_mesh_plotter
openmc_regular_mesh_plotter PublicForked from fusion-energy/openmc_regular_mesh_plotter
A Python package for plotting OpenMC regular mesh tally results with underlying geometry from neutronics simulations.
Python
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neutronics-workshop
neutronics-workshop PublicForked from fusion-energy/neutronics-workshop
A workshop covering a range of fusion relevant analysis and simulations with OpenMC, DAGMC, Paramak and other open source fusion neutronics tools
Jupyter Notebook
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openmc_cylindrical_mesh_plotter
openmc_cylindrical_mesh_plotter PublicForked from fusion-energy/openmc_cylindrical_mesh_plotter
Plots slices of openmc cylindrical mesh tallies results
Python
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