Investigation of convection heat transfer of supercritical water using ATHLET system code

SuperCritical Water-cooled Reactors (SCWRs) are one of six Generation-IV nuclear-reactor concepts. They are expected to have high thermal efficiencies within the range of 45-50% owing to the reactor's high pressures and outlet temperatures. Efforts have been made to study the supercritical phenomena both analytically and experimentally. The thermal-hydraulic computer code ATHLET (Analysis of THermal-hydraulics of LEaks and Transients) is used …