feature request: example usage with OpenMC

[shimwell]

Perhaps this is a step too far but the main reason I'm interested in this package is that I hope to use it to create the energy distribution of a neutron source term in OpenMC Monte Carlo particle transport code.

I've got one fleshed out over here

I would therefore be keen to add an example that shows how to do this.

Might be best to wait till there is a pip install for OpenMC