openmc.lib.Nuclide

class openmc.lib.Nuclide(*args)

Nuclide stored internally.

This class exposes a nuclide that is stored internally in the OpenMC solver. To obtain a view of a nuclide with a given name, use the openmc.lib.nuclides mapping.

Parameters:

index (int) – Index in the nuclides array.

Variables:

name (str) – Name of the nuclide, e.g. ‘U235’

collapse_rate(MT, temperature, energy, flux)

Calculate reaction rate based on group-wise flux distribution

Parameters:

• MT (int) – ENDF MT value of the desired reaction

• temperature (float) – Temperature in [K] at which to evaluate cross sections

• energy (iterable of float) – Energy group boundaries in [eV]

• flux (iterable of float) – Flux in each energy group (not normalized per eV)

Returns:

Reaction rate

Return type:

float