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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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dose map mesh neutronics plot regular structured tally

readme

N|Python

CI with install

PyPI

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

Features

:straight_ruler: Axis units in in helpful units mm, cm, m, km

:eyes: Supports all 3 viewing basis (xy, xz, yz)

:hocho: Automaticly finds central slice or allows user specified slice index

:dart: Supports all values (mean, std_dev etc)

:black_square_button: Adds outlines for geometry cells or material at different pixel resolution

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

:arrow_right_hook: supports further customisations throught matplotlib.rc()

:heavy_plus_sign: 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