openmc.Element¶

class openmc.Element(name='', xs=None)[source]¶

A natural element used in a material via <element>. Internally, OpenMC will expand the natural element into isotopes based on the known natural abundances.

Parameters:	name (str) – Chemical symbol of the element, e.g. Pu xs (str) – Cross section identifier, e.g. 71c
Variables:	name (str) – Chemical symbol of the element, e.g. Pu xs (str) – Cross section identifier, e.g. 71c scattering ({'data', 'iso-in-lab', None}) – The type of angular scattering distribution to use

expand()[source]¶

Expand natural element into its naturally-occurring isotopes.

Returns:	isotopes – Naturally-occurring isotopes of the element. Each item of the list is a tuple consisting of an openmc.Nuclide instance and the natural abundance of the isotope.
Return type:	list