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

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fusion-energy/openmc_regular_mesh_plotter

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A minimal Python package that plots slices of OpenMC regular mesh tallies with the model geometry.

Features

πŸ“ Axis units in in helpful units mm, cm, m, km

πŸ‘€ Supports all 3 viewing basis (xy, xz, yz)

πŸ”ͺ Automaticly finds central slice or allows user specified slice index

🎯 Supports all values (mean, std_dev etc)

πŸ”² Adds outlines for geometry cells or material at different pixel resolution

β†ͺ️ Customisable by passing keywords to underlying matplotlib functions colorbar, contour and imshow

β†ͺ️ supports further customisations throught matplotlib.rc()

βž• Add tally results together to get combined plot.

|drawing| drawing |

Local install

First you will need openmc installed, then you can install this package with pip

pip install openmc_regular_mesh_plotter

Usage

See the examples folder for example scripts

Web App

This package is deployed on xsplot.com as part of the openmc_plot suite of plotting apps

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

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