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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.
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
Files
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Readme
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Dependencies
.github/workflows/black.yml
actions
- actions/checkout v2 composite
- actions/setup-python v2 composite
- stefanzweifel/git-auto-commit-action v4 composite
- actions/checkout v2 composite
- codecov/codecov-action v2 composite
- actions/checkout v2 composite
- actions/setup-python v2 composite
pyproject.toml
pypi
- matplotlib >=3.4.2
- numpy >=1.21.1
- setuptools_scm *