Characteristics of thermal-hydraulic phenomena in the steam injector were examined. In experiments, a water jet from a nozzle of 5 mm diameter flowed into the condensing test section pipe concentrically. The inner diameter of the condensing section was 7, 10, or 20 mm and the length was 105 mm. Steam flowed into the peripheral space between the water jet and the inner wall of the test section and condensed on the ware jet surface. The radial and the axial distributions of velocity and temperature of the water jet were measured. Analyses by using the STAR-CD code were also performed. The temperature measured in the central portion of the water jet was higher than the predicted assuming the ordinary turbulent flow in a pipe. The temperature measured in the peripheral region was lower than the predicted. The radial temperature distribution measured was flatter than the predicted. When the steam condensation rate was large, the measured radial velocity distribution in the water jet was flatter than the predicted. In the case that the steam velocity was quite high, the velocity measured in the peripheral region was higher than that in the center portion. These results implied that the steam condensing on the water jet brought momentum in the water jet to result in more effective radial transport of heat and momentum. The STAR-CD code analyses to allow the interface between the wall that simulated the steam flow part and the water flow that stood for the water jet to move, i.e. creating momentum in-flux at the water jet interface, provided better results to support the experimental results. To increase the interfacial friction had a minor effect on the radial velocity distribution in the tested range.
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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 13—Study on Heat Transfer of Direct Condensation of Steam on Subcooled Water Jet Available to Purchase
Yuhki Takahashi,
Yuhki Takahashi
Kogakuin University, Hachioji, Tokyo, Japan
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Yasuo Koizumi,
Yasuo Koizumi
Kogakuin University, Hachioji, Tokyo, Japan
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Hiroyasu Ohtake,
Hiroyasu Ohtake
Kogakuin University, Hachioji, Tokyo, Japan
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Tohru Miyashita,
Tohru Miyashita
Kogakuin University, Hachioji, Tokyo, Japan
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Michitsugu Mori
Michitsugu Mori
Tokyo Electric Power Company, Yokohama, Japan
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Yuhki Takahashi
Kogakuin University, Hachioji, Tokyo, Japan
Yasuo Koizumi
Kogakuin University, Hachioji, Tokyo, Japan
Hiroyasu Ohtake
Kogakuin University, Hachioji, Tokyo, Japan
Tohru Miyashita
Kogakuin University, Hachioji, Tokyo, Japan
Michitsugu Mori
Tokyo Electric Power Company, Yokohama, Japan
Paper No:
ICONE14-89366, pp. 809-815; 7 pages
Published Online:
September 17, 2008
Citation
Takahashi, Y, Koizumi, Y, Ohtake, H, Miyashita, T, & Mori, M. "Development of Technologies on Innovative-Simplified Nuclear Power Plant Using High-Efficiency Steam Injectors: Part 13—Study on Heat Transfer of Direct Condensation of Steam on Subcooled Water Jet." 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. 809-815. ASME. https://doi.org/10.1115/ICONE14-89366
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