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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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updated setup and getting CI working #35

Closed shimwell closed 2 years ago

shimwell commented 2 years ago

this is just a start but I hope to get the CI working.

This should be possible now that fusion-neutronics-workflow releases now contain output files :tada:

shimwell commented 2 years ago

This PR should fix the failing CI https://github.com/fusion-energy/dagmc_geometry_slice_plotter/pull/19

codecov[bot] commented 2 years ago

Codecov Report

Merging #35 (6cd962d) into develop (5eeceab) will not change coverage. The diff coverage is 0.00%.

Impacted file tree graph

@@           Coverage Diff           @@
##           develop     #35   +/-   ##
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  Coverage     0.00%   0.00%           
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  Files            3       3           
  Lines          126     136   +10     
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- Misses         126     136   +10
Impacted Files Coverage Δ
regular_mesh_plotter/__init__.py 0.00% <0.00%> (ø)

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