Nuclear power plants are designed to avoid damage to their safety installations because of jet impingement when a pipe is ruptured. We have investigated the evaluation method for the design basis of protection of plants against effects of a postulated pipe rupture using the established standard of the American National Standards Institute (ANSI). The steam jet tests using particle image velocimetry and computational fluid dynamics (CFD) analysis were conducted for this verification. Spread angle of steam jet could be visualized. The jet spread angles were lower than 10 deg which was described in the ANSI standard. The ANSI standard was conservative for evaluations of the jet impact region compared to actual test and CFD results. However, it is desirable to use the conservative angle for evaluation of the jet fluid force. We could adequately evaluate the conservative jet fluid forces by the ANSI standard considering the spread suppression region and jet spread angle of 6 deg.
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2016 24th International Conference on Nuclear Engineering
June 26–30, 2016
Charlotte, North Carolina, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5003-9
PROCEEDINGS PAPER
Evaluation of Jet Impact Region and Fluid Force Generated From Ruptured Pipes: 3 — Evaluation of Established Standards Available to Purchase
Shiro Takahashi,
Shiro Takahashi
Hitachi, Ltd., Hitachi, Japan
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Noriyuki Takamura,
Noriyuki Takamura
Hitachi-GE, Hitachi, Japan
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Shun Watanabe
Shun Watanabe
CRIEPI, Yokosuka, Japan
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Qiang Xu
Hitachi-GE, Hitachi, Japan
Shiro Takahashi
Hitachi, Ltd., Hitachi, Japan
Noriyuki Takamura
Hitachi-GE, Hitachi, Japan
Ryo Morita
CRIEPI, Yokosuka, Japan
Yuta Uchiyama
CRIEPI, Yokosuka, Japan
Shun Watanabe
CRIEPI, Yokosuka, Japan
Paper No:
ICONE24-60317, V003T09A016; 6 pages
Published Online:
October 25, 2016
Citation
Xu, Q, Takahashi, S, Takamura, N, Morita, R, Uchiyama, Y, & Watanabe, S. "Evaluation of Jet Impact Region and Fluid Force Generated From Ruptured Pipes: 3 — Evaluation of Established Standards." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 3: Thermal-Hydraulics. Charlotte, North Carolina, USA. June 26–30, 2016. V003T09A016. ASME. https://doi.org/10.1115/ICONE24-60317
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