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fusion-energy
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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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refactored code into core and utils, improved examples and CI
#17
shimwell
closed
2 years ago
0
added examples to ci
#16
shimwell
closed
2 years ago
1
added pep formatter
#15
shimwell
closed
2 years ago
0
added draft example for each function
#14
shimwell
closed
2 years ago
0
Adding std dev plot
#13
shimwell
closed
2 years ago
0
added requested_units to functions
#12
shimwell
closed
2 years ago
1
Adding support for 3d regular meshes
#11
shimwell
closed
10 months ago
0
Adding contour lines
#10
shimwell
opened
2 years ago
1
Develop
#9
shimwell
closed
2 years ago
0
added rotate mesh option and started readme
#8
shimwell
closed
2 years ago
0
making use of dagmc_geometry_slice_plotter
#7
shimwell
closed
2 years ago
0
adding vtk writing
#6
shimwell
closed
2 years ago
1
Accepting tally inputs
#5
shimwell
closed
2 years ago
0
adds get_extent function
#4
shimwell
closed
2 years ago
0
add get_extent function
#3
shimwell
closed
2 years ago
0
Move the mesh data from 0,0
#2
shimwell
closed
2 years ago
2
added inital slice plot, mesh plot
#1
shimwell
closed
2 years ago
0
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