American Nuclear Society
Home

Home / Publications / Journals / Fusion Science and Technology / Volume 29 / Number 4

Critical Heat Flux of Subcooled Flow Boiling in Swirl Tubes Relevant to High-Heat-Flux Components

Fujio Inasaka, Hideki Nariai

Fusion Science and Technology / Volume 29 / Number 4 / July 1996 / Pages 487-498

Technical Paper / Blanket Engineering / dx.doi.org/10.13182/FST96-A30692

It is necessary to accurately determine the critical heat flux (CHF) of cooling systems used infusion 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 nonuniformity 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.