Regarding the Japan Sodium-cooled Fast Reactor, a multi-elbow piping system is adopted for its cold-legs. Flow Induced Vibration (FIV) is considered to be caused by complex flow with very high velocity in the elbows. In this study, pressure measurement test of a single elbow flow is conducted to find out pressure fluctuation characteristic which is related to the elbow turbulent flow and lead potentially to the FIV. Two types of experimental loops, that is, 1/7 and 1/15-scale setup simulating the JSFR cold-leg pipings, are used for pressure measurement, and a distinguishing peak can be seen in the power spectrum density profile of pressure fluctuation obtained where flow separation occurs and at the downstream from it. This characteristics of pressure fluctuation is obtained from the two different scale experiments, and the scale effect is not found in terms of the pressure fluctuation.
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18th International Conference on Nuclear Engineering
May 17–21, 2010
Xi’an, China
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-4932-3
PROCEEDINGS PAPER
Pressure Measurement Test of Single Elbow Simulating Na Cooled Fast Reactor Cold-Leg Piping Available to Purchase
Shinji Ebara,
Shinji Ebara
Tohoku University, Sendai, Miyagi, Japan
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Yuta Aoya,
Yuta Aoya
Tohoku University, Sendai, Miyagi, Japan
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Tsukasa Sato,
Tsukasa Sato
Tohoku University, Sendai, Miyagi, Japan
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Hidetoshi Hashizume,
Hidetoshi Hashizume
Tohoku University, Sendai, Miyagi, Japan
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Kazuhisa Yuki,
Kazuhisa Yuki
Tokyo University of Science, Yamaguchi, Yamaguchi, Japan
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Kosuke Aizawa,
Kosuke Aizawa
Japan Atomic Energy Agency, Ibaraki, Japan
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Hidemasa Yamano
Hidemasa Yamano
Japan Atomic Energy Agency, Ibaraki, Japan
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Shinji Ebara
Tohoku University, Sendai, Miyagi, Japan
Yuta Aoya
Tohoku University, Sendai, Miyagi, Japan
Tsukasa Sato
Tohoku University, Sendai, Miyagi, Japan
Hidetoshi Hashizume
Tohoku University, Sendai, Miyagi, Japan
Kazuhisa Yuki
Tokyo University of Science, Yamaguchi, Yamaguchi, Japan
Kosuke Aizawa
Japan Atomic Energy Agency, Ibaraki, Japan
Hidemasa Yamano
Japan Atomic Energy Agency, Ibaraki, Japan
Paper No:
ICONE18-29719, pp. 705-713; 9 pages
Published Online:
April 8, 2011
Citation
Ebara, S, Aoya, Y, Sato, T, Hashizume, H, Yuki, K, Aizawa, K, & Yamano, H. "Pressure Measurement Test of Single Elbow Simulating Na Cooled Fast Reactor Cold-Leg Piping." Proceedings of the 18th International Conference on Nuclear Engineering. 18th International Conference on Nuclear Engineering: Volume 4, Parts A and B. Xi’an, China. May 17–21, 2010. pp. 705-713. ASME. https://doi.org/10.1115/ICONE18-29719
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