Analysis and scaling of coupled neutronic thermal hydraulic instabilities of supercritical water cooled reactor

Abstract

Present thesis work primarily focuses on the analysis of flow instabilities in one of the most powerful concepts under Gen IV nuclear reactor technology namely the supercritical water cooled reactor SCWR Safety is the primary concern in nuclear reactors and the study of flow instabilities is an important aspect of safety assessment To facilitate the study of complex phenomena in the laboratory a method for designing a downscaled model has been proposed here for both natural as well as for