Next-generation nuclear reactor systems have been under development aiming at simplified system and improvement of safety and credibility. One of the innovative technologies is the supersonic steam injector, which has been investigated as one of the most important component of the next-generation nuclear reactor. The steam injector has functions of a passive pump without large motor or turbo-machinery and a high efficiency heat exchanger. The performances of the supersonic steam injector as a pump and a heat exchanger are dependent on direct contact condensation phenomena between a supersonic steam and a sub-cooled water jet. In previous studies of the steam injector, there are studies about the operating characteristics of steam injector and about the direct contact condensation between static water pool and steam in atmosphere. However, there is a little study about the turbulent heat transfer and flow behavior under the great shear stress. In order to examine the heat transfer and flow behavior in supersonic steam injector, it is necessary to measure the spatial temperature distribution and velocity in detail. The present study, visible transparent supersonic steam injector is used to obtain the axial pressure distributions in the supersonic steam injector, as well as high speed visual observation of water jet and steam interface. The experiments are conducted with and without non-condensable gas. The experimental results of the interfacial flow behavior between steam and water jet are obtained. It is experimentally clarified that an entrainment exists on the water jet surface. It is also clarified that discharge pressure is depended on the steam supply pressure, the inlet water flow rate, the throat diameter and non-condensable flow rate. Finally a heat flux is estimated about 19MW/m2 without non-condensable gas condition in steam.
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14th International Conference on Nuclear Engineering
July 17–20, 2006
Miami, Florida, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4244-4
PROCEEDINGS PAPER
Development of Technologies on Innovative-Simplified Nuclear Power Plant Using High-Efficiency Steam Injectors: Part 12—Evaluations of Spatial Distributions of Flow and Heat Transfer in Steam Injector
Yutaka Abe,
Yutaka Abe
University of Tsukuba, Tsukuba, Ibaraki, Japan
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Yujiro Kawamoto,
Yujiro Kawamoto
University of Tsukuba, Tsukuba, Ibaraki, Japan
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Chikako Iwaki,
Chikako Iwaki
Toshiba Corporation, Kawasaki, Kanagawa, Japan
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Tadashi Narabayashi,
Tadashi Narabayashi
Hokkaido University, Sapporo, Japan
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Michitsugu Mori,
Michitsugu Mori
Tokyo Electric Power Company, Yokohama, Kanagawa, Japan
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Shuichi Ohmori
Shuichi Ohmori
Tokyo Electric Power Company, Yokohama, Kanagawa, Japan
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Yutaka Abe
University of Tsukuba, Tsukuba, Ibaraki, Japan
Yujiro Kawamoto
University of Tsukuba, Tsukuba, Ibaraki, Japan
Chikako Iwaki
Toshiba Corporation, Kawasaki, Kanagawa, Japan
Tadashi Narabayashi
Hokkaido University, Sapporo, Japan
Michitsugu Mori
Tokyo Electric Power Company, Yokohama, Kanagawa, Japan
Shuichi Ohmori
Tokyo Electric Power Company, Yokohama, Kanagawa, Japan
Paper No:
ICONE14-89417, pp. 827-834; 8 pages
Published Online:
September 17, 2008
Citation
Abe, Y, Kawamoto, Y, Iwaki, C, Narabayashi, T, Mori, M, & Ohmori, S. "Development of Technologies on Innovative-Simplified Nuclear Power Plant Using High-Efficiency Steam Injectors: Part 12—Evaluations of Spatial Distributions of Flow and Heat Transfer in Steam Injector." Proceedings of the 14th International Conference on Nuclear Engineering. Volume 3: Structural Integrity; Nuclear Engineering Advances; Next Generation Systems; Near Term Deployment and Promotion of Nuclear Energy. Miami, Florida, USA. July 17–20, 2006. pp. 827-834. ASME. https://doi.org/10.1115/ICONE14-89417
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