The heat transfer tubes in steam generator of High Temperature Reactor-Pebble bed Modules (HTR-PM) suffer a high-speed and high temperature Helium flow environment. To avoid high thermal stress and decrease the fluid-induced vibration, tubes are packed in the form of rectangular tubes bundles. The empirical formulas of flow-induced vibration in ASME code are applicable to circular cylinder and incompressible media, which is not available for the proposed problem. In the present paper, rectangular tubes bundles are simplified as square cylinder with specific stiffness. The vibration of six square cylinders with horizontal and vertical arrangements are analyzed in displacement and frequency. The results show that the six square cylinders reveal same vibration amplitude and frequency, but different balance positions. For the horizontal arrangement and the vertical arrangement, according to the different balance positions, the balance position boundary line can be drawn. The cylinders at two sides of the balance position boundary line are closer to each other, where collisions or damages are easy to occur.
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2018 26th International Conference on Nuclear Engineering
July 22–26, 2018
London, England
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
978-0-7918-5148-7
PROCEEDINGS PAPER
A Flow-Induced Vibration Study on the Multiple Rectangular Tubes Bundles for Steam Generator Outlet Pipes of HTR-PM
Zhao Jiaqing,
Zhao Jiaqing
Tsinghua University, Beijing, China
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Zhang Yiyang,
Zhang Yiyang
Tsinghua University, Beijing, China
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Wu Xinxin
Wu Xinxin
Tsinghua University, Beijing, China
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Song Yu
Tsinghua University, Beijing, China
Zhou Qin
Tsinghua University, Beijing, China
Zhao Jiaqing
Tsinghua University, Beijing, China
Zhang Yiyang
Tsinghua University, Beijing, China
Wu Xinxin
Tsinghua University, Beijing, China
Paper No:
ICONE26-81229, V06AT08A018; 7 pages
Published Online:
October 24, 2018
Citation
Yu, S, Qin, Z, Jiaqing, Z, Yiyang, Z, & Xinxin, W. "A Flow-Induced Vibration Study on the Multiple Rectangular Tubes Bundles for Steam Generator Outlet Pipes of HTR-PM." Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6A: Thermal-Hydraulics and Safety Analyses. London, England. July 22–26, 2018. V06AT08A018. ASME. https://doi.org/10.1115/ICONE26-81229
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