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Thermal-Hydraulics Program in Support of Canadian...
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Thermal-Hydraulics Program in Support of Canadian SCWR Concept Development

Abstract

The thermal-hydraulics program in support of the development of the Canadian supercritical water-cooled reactor (SCWR) concept has 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 (CO2), or refrigerant flows. Data from these experiments have led to …

Authors

Leung LKH; Dominguez AN

Volume

4

Publisher

ASME International

Publication Date

January 1, 2018

DOI

10.1115/1.4037807

Conference proceedings

Journal of Nuclear Engineering and Radiation Science

Issue

1

ISSN

2332-8983