openmc.Nuclide

class openmc.Nuclide(name='', xs=None)

A nuclide that can be used in a material.

Parameters:

• name (str) – Name of the nuclide, e.g. U-235
• xs (str) – Cross section identifier, e.g. 71c

Variables:

• name (str) – Name of the nuclide, e.g. U-235
• xs (str) – Cross section identifier, e.g. 71c
• zaid (int) – 1000*(atomic number) + mass number. As an example, the zaid of U-235 would be 92235.
• scattering ('data' or 'iso-in-lab' or None) – The type of angular scattering distribution to use