Conference
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