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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

📏 Axis units in in helpful units mm, cm, m, km

👀 Supports all 3 viewing basis (xy, xz, yz)

🔪 Automaticly finds central slice or allows user specified slice index

🎯 Supports all values (mean, std_dev etc)

🔲 Adds outlines for geometry cells or material at different pixel resolution

↪️ Customisable by passing keywords to underlying matplotlib functions colorbar, contour and imshow

↪️ supports further customisations throught matplotlib.rc()

➕ 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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