Study on Specifics of Forced-Convective Heat Transfer in Supercritical Carbon Dioxide

Author:

Saltanov Eugene1,Pioro Igor1,Mann David1,Gupta Sahil1,Mokry Sarah1,Harvel Glenn1

Affiliation:

1. Faculty of Energy Systems and Nuclear Science, University of Ontario Institute of Technology, 2000 Simcoe Street North, Oshawa, ON L1H 7K4, Canada e-mail:

Abstract

The appropriate description of heat transfer to coolants at the supercritical state is limited by the current understanding. Thus, this poses one of the main challenges in the development of supercritical-fluids applications for Generation-IV reactors. Since the thermodynamic critical point of water is much higher than that of carbon dioxide (CO2), it is more affordable to run heat-transfer experiments in supercritical CO2. The data for supercritical CO2 can be later scaled and used for supercritical water-based reactor designs. The objective of this paper is, therefore, to discuss the basis for comparison of relatively recent experimental data on supercritical CO2 obtained at the facilities of the Korea Atomic Energy Research Institute (KAERI) and Chalk River Laboratories (CRL) of the Atomic Energy of Canada Limited (AECL). Based on the available instrumental error, a thorough analysis of experimental errors in wall- and bulk-fluid temperatures and heat transfer coefficient was conducted. A revised heat-transfer correlation for the CRL data is presented. A dimensional criterion for the onset of the deteriorated heat transfer in the form of a linear relation between heat flux and mass flux is proposed. A preliminary heat-transfer correlation for the joint CRL and KAERI datasets is presented.

Publisher

ASME International

Subject

Nuclear Energy and Engineering,Radiation

Reference40 articles.

1. Heat Transfer to Water and Steam at Variable Specific Heat (at Near-Critical Region);J. Tech. Phys.,1957

2. Heat Transfer to Water, Oxygen and Carbon Dioxide in Near Critical Region;Therm. Eng.,1959

3. Bishop, A. A., Sandberg, R. O., and Tong, L. S., 1964, “Forced Convection Heat Transfer to Water at Near-Critical Temperatures and Supercritical Pressures,” Report No. WCAP-2056, Westinghouse Electric Corporation, Atomic Power Division, December, Pittsburgh, PA, 85 pp.

4. Heat Transfer to Supercritical Water in Smooth-Bore Tubes;J. Heat Transfer Trans. ASME Ser. C,1965

5. Heat Transfer with Rising and Falling Flows of Water in Tubes of Small Diameter at Supercritical Pressures;Therm. Eng.,1971

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