The heat transfer tube bundles of the steam generator in high temperature reactor pebble bed module (HTR-PM) are subjected to high speed helium flow, which might lead to vortex-induced vibration (VIV). In the present paper, to investigate the vibration of square cylinder under flow effect, vortex shedding phenomena of a stationary square cylinder at a high Reynolds number equal to 6.8 × 104 is simulated by detached eddy simulation (DES) turbulence models. A comparatively close agreement with previous experimental results is achieved. Combining computational fluid dynamics (CFD) and computational structural dynamics (CSD) methods, a fluid-structure-interaction (FSI) model for VIV of the square cylinder is then established, and vibration response perpendicular to flow direction were investigated. Moreover, the safe range of the natural frequency of the square cylinder to avoid synchronized vibration with VIV is analyzed. The results of this paper can provide an important guidance to the design of the heat transfer tubes and their supports in HTR-PM.
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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:
978-0-7918-5004-6
PROCEEDINGS PAPER
Numerical Study on a Single Square Cylinder Subjected to Vortex-Induced Vibration in HTR-PM
Qiankun Xiao,
Qiankun Xiao
Tsinghua University, Beijing, China
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Xiaoxin Wang,
Xiaoxin Wang
Tsinghua University, Beijing, China
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Xiaowei Luo,
Xiaowei Luo
Tsinghua University, Beijing, China
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Xinxin Wu
Xinxin Wu
Tsinghua University, Beijing, China
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Qiankun Xiao
Tsinghua University, Beijing, China
Li Shi
Tsinghua University, Beijing, China
Xiaoxin Wang
Tsinghua University, Beijing, China
Xiaowei Luo
Tsinghua University, Beijing, China
Xinxin Wu
Tsinghua University, Beijing, China
Paper No:
ICONE24-60230, V004T10A008; 7 pages
Published Online:
October 25, 2016
Citation
Xiao, Q, Shi, L, Wang, X, Luo, X, & Wu, X. "Numerical Study on a Single Square Cylinder Subjected to Vortex-Induced Vibration in HTR-PM." Proceedings of the 2016 24th International Conference on Nuclear Engineering. Volume 4: Computational Fluid Dynamics (CFD) and Coupled Codes; Decontamination and Decommissioning, Radiation Protection, Shielding, and Waste Management; Workforce Development, Nuclear Education and Public Acceptance; Mitigation Strategies for Beyond Design Basis Events; Risk Management. Charlotte, North Carolina, USA. June 26–30, 2016. V004T10A008. ASME. https://doi.org/10.1115/ICONE24-60230
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