In the steam generator of the prototype FBR (Fast Breeder Reactor) in Japan, heat exchange tubes of helical coil type are utilized. The gas-liquid two-phase flows in the helical coil tube have different characteristic from straight tubes due to the effects of centrifugal acceleration in the curved tubes. In our study, the interfacial structure of the gas-liquid two-phase flows in the helical coil tube is visualized to provide the flow pattern map. Simultaneously, the pressure loss and its local fluctuation are measured in order to investigate the dynamic characteristics of the two-phase flow appearing in the helical coil tube. The result reveals that the bubbly flow regime extends and the stratified flow vanishes compared the gas-liquid flow in a horizontal straight tube. Moreover, the slug flow has asymmetric structure due to the effect of centrifugal acceleration. On the contrary the pressure loss is basically not remarkably different from the straight tube except the fact that the pressure has a high fluctuation component.
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ASME/JSME 2003 4th Joint Fluids Summer Engineering Conference
July 6–10, 2003
Honolulu, Hawaii, USA
Conference Sponsors:
- Fluids Engineering Division
ISBN:
0-7918-3696-7
PROCEEDINGS PAPER
Flow Structure and Pressure Loss of Two-Phase Flow in Helically Coiled Tubes
Masa-aki Ishikawa,
Masa-aki Ishikawa
Fukui University, Fukui-shi, Japan
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Hiroshi Oiwa,
Hiroshi Oiwa
Fukui University, Fukui-shi, Japan
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Kosuke Sakai,
Kosuke Sakai
Fukui University, Fukui-shi, Japan
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Yuichi Murai,
Yuichi Murai
Fukui University, Fukui-shi, Japan
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Shin-ichi Toda,
Shin-ichi Toda
Japan Nuclear Cycle Development Institute, Tsuruga-shi, Japan
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Kiyoshi Tamayama,
Kiyoshi Tamayama
Japan Nuclear Cycle Development Institute, Tsuruga-shi, Japan
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Fujio Yamamoto
Fujio Yamamoto
Fukui University, Fukui-shi, Japan
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Masa-aki Ishikawa
Fukui University, Fukui-shi, Japan
Hiroshi Oiwa
Fukui University, Fukui-shi, Japan
Kosuke Sakai
Fukui University, Fukui-shi, Japan
Yuichi Murai
Fukui University, Fukui-shi, Japan
Shin-ichi Toda
Japan Nuclear Cycle Development Institute, Tsuruga-shi, Japan
Kiyoshi Tamayama
Japan Nuclear Cycle Development Institute, Tsuruga-shi, Japan
Fujio Yamamoto
Fukui University, Fukui-shi, Japan
Paper No:
FEDSM2003-45376, pp. 1453-1458; 6 pages
Published Online:
February 4, 2009
Citation
Ishikawa, M, Oiwa, H, Sakai, K, Murai, Y, Toda, S, Tamayama, K, & Yamamoto, F. "Flow Structure and Pressure Loss of Two-Phase Flow in Helically Coiled Tubes." Proceedings of the ASME/JSME 2003 4th Joint Fluids Summer Engineering Conference. Volume 1: Fora, Parts A, B, C, and D. Honolulu, Hawaii, USA. July 6–10, 2003. pp. 1453-1458. ASME. https://doi.org/10.1115/FEDSM2003-45376
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