Critical heat flux of subcooled flow boiling in swirl tubes relevant to high-heat-flux components
- Ship Research Inst., Tokyo (Japan)
- Univ. of Tsukuba, Ibaraki (Japan)
It is necessary to accurately determine the critical heat flux (CHF) of cooling systems used in fusion reactors. Currently, sufficiently accurate CHF correlations for one-sided heating have not been established. A design method for subcooled boiling cooling systems using swirl tubes is described. From a review of existing work under uniform heating conditions, the correlations of Gunther and Nariai-Inasaka are recommended for smooth and swirl flow, respectively. The effects of thermal conductivity and geometry of the cooling sections on both the nouniformity factor and the peaking factor were investigated by solving a heat conduction equation. For swirl flow under one-sided heating, the CHF multiplier increases with the increasing nonuniformity factor. Design criteria for subcooled boiling swirl-tube cooling systems are presented. 33 refs., 13 figs., 4 tabs.
- OSTI ID:
- 374456
- Journal Information:
- Fusion Technology, Journal Name: Fusion Technology Journal Issue: 4 Vol. 29; ISSN 0748-1896; ISSN FUSTE8
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
42 ENGINEERING
70 PLASMA PHYSICS AND FUSION TECHNOLOGY
99 GENERAL AND MISCELLANEOUS
CRITICAL HEAT FLUX
DESIGN
FLUID FLOW
MATHEMATICAL MODELS
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
SUBCOOLED BOILING
THERMAL CONDUCTION
THERMAL CONDUCTIVITY
THERMONUCLEAR REACTORS
TUBES
VORTEX FLOW