Improved Understanding toward Sliding Bubble Effect on Wall Heat Transfer in Subcooled Boiling Flow

Journal Article · Fri Jul 01 04:00:00 EDT 2016 · Transactions of the American Nuclear Society

OSTI ID:23042949

Yoo, Junsoo ^[1]; Estrada-Perez, Carlos E.; Hassan, Yassin A. ^[2]

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1. Idaho National Laboratory: 2525 North Freemont Ave./P.O.Box 3860, Idaho Falls, ID 83415-3870 (United States)
2. Department of Nuclear Engineering, Texas A and M University, 253 Bizzell West, College Station, TX 77843-3133 (United States)

The significance of bubble sliding on wall heat transfer under boiling and condensing conditions has consistently been reported by previous researchers, causing increasing attention within boiling heat transfer community. The authors' recent work for subcooled flow boiling experiment, also clearly shows the strong influence of sliding bubbles in wall heat transfer. However, despite the importance as well as the interest for the sliding bubbles both in experiment and CFD modelling, the mechanism of wall heat transfer induced by sliding bubbles has still barely been known. This mainly results from the fact that proper experimental data and physical insight based on them are largely lacking. This paper presents the authors' work to improve the insight toward the wall heat transfer mechanism associated with sliding bubbles. In particular, effort has been dedicated to identifying the knowledge gap between the actual physics and the CFD boiling models. Specifically, of major interest is the 'wall area of bubble influence' which is one of the important factors considered in most wall heat flux partitioning models to evaluate the heat transfer process like quenching. The experimental observation presented in this paper reveals the limitation of existing models and suggests the new physical insight needed to improve them. (authors)

• OSTI ID: 23042949
• Journal Information: Transactions of the American Nuclear Society, Journal Name: Transactions of the American Nuclear Society Vol. 115; ISSN 0003-018X
• Country of Publication: United States
• Language: English

Related Subjects

22 GENERAL STUDIES OF NUCLEAR REACTORS
42 ENGINEERING
BUBBLES
COMPUTERIZED SIMULATION
HEAT FLUX
HEAT TRANSFER
PARTITION
QUENCHING
SUBCOOLED BOILING