Characteristics of Heat Transfer During Boiling of Liquid Metal in the Fuel Assemblies of Fast Reactors in Emergency Regimes

Thermohydraulic studies of alkali liquid metal coolants for justification of nuclear power facilities

“…To exclude the development of an emergency caused by an operational occurrence with simultaneous loss of power for the reactor coolant pumps and a failure of the reactor scram rods (an ULOF accident), a design solution has been proposed with a 'sodium plenum' arranged above the reactor core. Comparing the calculation and experiment results has shown the possibility of heat removal by the boiling coolant in a model FA with a 'sodium plenum' during thermal loads of 10% to 15% and the sodium flow rate level of about 5% of the nominal values (Sorokin et al 2018).…”

“…It has been shown that long-term cooling of the core is conceptually possible in emergency modes involving boiling of liquid metals. Heat transfer during boiling of liquid metals in fuel rod bundles has been studied, the effects of the fuel rod surface roughness on the development of the boiling process has been investigated, and a diagram of the twophase liquid metal flow patterns in fuel rod bundles has been plotted [Sorokin et al 2018[Sorokin et al , 2019.…”