Mitigation of Heat Transfer Deterioration in Supercritical Water Using Vortex Generator

Research output: Chapters, Conference Papers, Creative and Literary WorksRGC 32 - Refereed conference paper (with host publication)peer-review

1 Scopus Citations
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Detail(s)

Original languageEnglish
Title of host publication2017 International Congress on Advances in Nuclear Power Plants, ICAPP2017 - A New Paradigm in Nuclear Power Safety, Proceedings
PublisherInternational Congress on Advances in Nuclear Power Plants, ICAPP
ISBN (print)9784890471676
Publication statusPublished - Apr 2017

Conference

Title2017 International Congress on Advances in Nuclear Power Plants (ICAPP 2017)
LocationHotel Fujita Fukui and The Westin Miyako Kyoto
PlaceJapan
CityFukui and Kyoto
Period24 - 28 April 2017

Abstract

Supercritical water reactor (SCWR) is one of the most promising generation IV nuclear reactor systems, thanks to its high thermal efficiency and simplicity. Although there is no phase change in water at supercritical pressure, strong variation of thermal-physical properties exists in the vicinity of the pseudocritical point, which might have a great effect on the behavior of heat transfer. Heat transfer deterioration (HTD) is one of the main issues in the design of SCWR, which has been studied by lots of researchers. However, nearly no effective method has been proposed to mitigate HTD in supercritical water. In this paper, vortex generators (VGs) are used in annular channels to investigate HTD phenomenon of supercritical water at high heat fluxes and low mass fluxes with Shear Stress Transport (SST) k-ω model in commercial software Fluent 15.0. The effects of VG size, number and distance on HTD mitigation are investigated. The results show that the VG can significantly decrease the peak of temperature along the fuel rod. The size of VG has little effect on HTD mitigation. The number of VG has great effect on HTD mitigation. Two VGs can achieve obvious mitigation with lowest cost. The distance of VGs also has great effect on the HTD mitigation. There exists an optimal distance to achieve the largest decrease of the peak temperature. Heat transfer coefficient is increased at the positions where VGs are installed. The pressure drops is very small and can be ignored when compared the supercritical operating pressure.

Bibliographic Note

"Full text of this publication does not contain sufficient affiliation information. With consent from the author(s) concerned, the Research Unit(s) information for this record is based on the existing academic department affiliation of the author(s)”

Citation Format(s)

Mitigation of Heat Transfer Deterioration in Supercritical Water Using Vortex Generator. / Cheng, Hui; Zhao, Jiyun.
2017 International Congress on Advances in Nuclear Power Plants, ICAPP2017 - A New Paradigm in Nuclear Power Safety, Proceedings. International Congress on Advances in Nuclear Power Plants, ICAPP, 2017.

Research output: Chapters, Conference Papers, Creative and Literary WorksRGC 32 - Refereed conference paper (with host publication)peer-review