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Thermal-Hydraulics Program in Support of Canadian SCWR Concept Development

[+] Author and Article Information
Laurence K.H. Leung

Canadian Nuclear Laboratories, 286 Plant Road, Chalk River, Ontario K0J 1J0 Canada
laurence.leung@cnl.ca

Armando Nava Dominguez

Canadian Nuclear Laboratories, 286 Plant Road, Chalk River, Ontario K0J 1J0 Canada
armando.nava@cnl.ca

1Corresponding author.

ASME doi:10.1115/1.4037807 History: Received April 28, 2017; Revised August 25, 2017

Abstract

The thermal-hydraulics program in support of the development of the Canadian Super-Critical Water-cooled Reactor (SCWR) concept have undergone several phases. It focused on key parameters such as heat transfer, critical flow and stability of fluids at supercritical pressures. Heat-transfer experiments were performed with tubes, annuli and bundles in water, carbon dioxide or refrigerant flows. Data from these experiments have led to enhancement in understanding of the phenomena, improved prediction methods and verified analytical tools. In addition, these experiments facilitated the investigation of separate effects on heat transfer (such as geometry, diameter, spacing device, transient, etc.). Chocking flow characteristics were studied experimentally with sharp-edged nozzles of two different sizes of opening. Experimental data have been applied in improving the critical-flow correlation in support of accident analyses. A one-dimensional analytical model for instability phenomena has been developed and assessed against the latest experimental data for quantifying the prediction capability and applicability.

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