Heat transfer analysis of internally-cooled fuel element☆

Abstract A complete mathematical analysis of an internally-cooled fast breeder reactor fuel element is developed. The thermohydraulics of the coolant, clad and fuel are studied for both sodium-cooled and helium-cooled designs. Comparisons with the conventional rod-type fuel element show that this internally-cooled fuel, which should have considerably improved duct creep performance, results in better overall fuel thermohydraulic performance as well.