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Research Papers

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

[+] Author and Article Information
Eugene Saltanov

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

Igor Pioro

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

David Mann

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

Sahil Gupta

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

Sarah Mokry

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

Glenn Harvel

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

Manuscript received August 2, 2014; final manuscript received September 29, 2014; published online February 9, 2015. Assoc. Editor: Joseph Miller.

ASME J of Nuclear Rad Sci 1(1), 011008 (Feb 09, 2015) (8 pages) Paper No: NERS-14-1032; doi: 10.1115/1.4026395 History: Received August 02, 2014; Accepted November 14, 2014; Online February 09, 2015

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.

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References

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Figures

Grahic Jump Location
Fig. 1

Pressure-temperature diagram for water

Grahic Jump Location
Fig. 2

Pressure-temperature diagram for CO2

Grahic Jump Location
Fig. 3

Experimental versus calculated Nub based on Eq. (6) and Q-approach (CRL and KAERI data)

Grahic Jump Location
Fig. 4

Experimental versus calculated HTCs based on Eq. (2) and T-approach (CRL data)

Grahic Jump Location
Fig. 5

Experimental versus calculated HTCs based on Eq. (2) and Q-approach (CRL data)

Grahic Jump Location
Fig. 6

Experimental versus calculated Tw based on Eq. (2) and Q-approach (CRL data)

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