Progress of Thermal-hydraulic Research on SCWR in NPIC

Abstract

For advantages of higher efficiency of thermal cycle, simpler primary coolant circuit etc, Supercritical Water Reactor (SCWR) is much competitive in the Generation-Ⅳ nuclear system. Based on the supercritical water reactor engineering, NPIC has started related numerical analysis, test technology research, test facility design and some experimental researches of thermal hydraulics of supercritical water since 2005. The progress of thermal hydraulic research on SCW in NPIC in the past five years, will be introduced briefly, included numerical research of SCW thermal hydraulic performance, test technology research, design and construction of thermal hydraulic test facilities, and related experimental research of SCW flow resistance and heat transfer behavior.