openmc.Nuclide¶

class openmc.Nuclide(name='')[source]¶

A nuclide that can be used in a material.

Parameters:	name (str) – Name of the nuclide, e.g. U235
Variables:	name (str) – Name of the nuclide, e.g. U235 scattering ('data' or 'iso-in-lab' or None) – The type of angular scattering distribution to use