The latest review of chf enhancement methods in nuclear systems

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

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Detail(s)

Original languageEnglish
Title of host publicationInternational Congress on Advances in Nuclear Power Plants (ICAPP 2018)
PublisherAmerican Nuclear Society
Pages172-181
ISBN (Electronic)9780894487453
ISBN (Print)9780894487552, 9781510861206
Publication statusPublished - Apr 2018

Conference

Title2018 International Congress on Advances in Nuclear Power Plants, ICAPP 2018
PlaceUnited States
CityCharlotte
Period8 - 11 April 2018

Abstract

External reactor vessel cooling (ERVC) is proved as a necessary system in in-vessel retention management in the nuclear power plant to transfer the heat from failed core to outside vessel, in the aim of preserving intact vessel and avoiding severe accidents. To provide advanced safety guarantee for the next generation of nuclear power plant, a greater designed safety margin should be considered and proposed, such as increasing the tolerance of high heat flux by using advanced materials of the vessel, insulated structures between reactor core and the vessel, and superior coolant in ERVC system. As long as the heat flux of the reactor vessel wall emerged from melt-core does not go beyond the maximum limitation-Critical Heat Flux (CHF), the decay heat can be dissipated timely and thus the reactor can be cooled down without releasing radiation products. In this case, increasing critical heat flux by various approaches is deemed essential also attract intensive studies in nuclear systems. In fact, the research of the enhancement of critical heat flux has a long history, with extensive experiments and simulations devoted in the last several decades to seeking for methods to expand thermal margin and it continues to be a promising topic in heat transfer research fields. In this paper, we present a comprehensive overview of CHF enhancement experiments, focusing on four broad categories of approaches. The first approach considered is amelioration of fluid properties by adding nanoparticles into the base fluid, by which both flow boiling and pool boiling achieve significant improvements in CHF. The second prevailing method recently is surface modifications by various advanced techniques. Third, we review the effect of various modified channel structures on the boiling process. Finally, some creative and notable hybrid techniques are presented. Based on this review of the state-of-The-Art in CHF enhancement, future research directions are also proposed.

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)

The latest review of chf enhancement methods in nuclear systems. / Xie, Shangzhen; Zhao, Jiyun.
International Congress on Advances in Nuclear Power Plants (ICAPP 2018). American Nuclear Society, 2018. p. 172-181.

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