Assessment of Supercritical Heat-transfer Correlations Against AECL Database for Tubes

Abstract

Thermalhydraulic characteristics at supercritical water-flow conditions need to be investigated in support of the fuel-bundle design and qualification, and safety analysis for the supercritical water-cooled reactor (SCWR). An experimental database on supercritical heat transfer for water flow (both upward and downward) in tubes has been compiled from published literature. Four existing supercritical heat transfer correlations were assessed against the AECL database for water flow in tubes. The objective of this paper is to present the database and the assessment results of the existing correlations against the supercritical heat-transfer database.