openmc.data.decay_energy

openmc.data.decay_energy(nuclide: str)[source]

Get decay energy value resulting from the decay of a nuclide

This function relies on data stored in a depletion chain. Before calling it for the first time, you need to ensure that a depletion chain has been specified in openmc.config[‘chain_file’].

New in version 0.13.3.

Parameters

nuclide (str) – Name of nuclide, e.g., ‘H3’

Returns

Decay energy of nuclide in [eV]. If the nuclide is stable, a value of 0.0 is returned.

Return type

float