In steam generators and other heat exchangers, there are a lot of tube bundles subjected to two-phase cross-flow. The fluctuating pressure on tube bundle caused by turbulence can induce structural vibration. The experimental data from a U-tube bundle of steam generator in air-water flow loop are analyzed in this work. The different upper bounds of buffeting force are used to calculate the turbulence buffeting response of U-tubes, and the calculation results are compared with the experimental results. The upper bounds of buffeting force include one upper bound based on single-phase flow, and two upper bounds based on two-phase flow. It is shown that the upper bound based on single-phase flow seriously underestimated the turbulence excitation, the calculated vibration response is much less than the experimental measurement. On the other hand, the vibration response results calculated with the upper bounds based on two-phase flow are closer to the measured results under most circumstances.
Skip Nav Destination
ASME 2017 Pressure Vessels and Piping Conference
July 16–20, 2017
Waikoloa, Hawaii, USA
Conference Sponsors:
- Pressure Vessels and Piping Division
ISBN:
978-0-7918-5797-7
PROCEEDINGS PAPER
Research on Two-Phase Flow Induced Vibration Characteristics of U-Tube Bundles Available to Purchase
Jiang Nai-bin,
Jiang Nai-bin
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Gao Li-xia,
Gao Li-xia
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Huang Xuan,
Huang Xuan
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Zang Feng-gang,
Zang Feng-gang
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Xiong Fu-rui
Xiong Fu-rui
Nuclear Power Institute of China, Chengdu, China
Search for other works by this author on:
Jiang Nai-bin
Nuclear Power Institute of China, Chengdu, China
Gao Li-xia
Nuclear Power Institute of China, Chengdu, China
Huang Xuan
Nuclear Power Institute of China, Chengdu, China
Zang Feng-gang
Nuclear Power Institute of China, Chengdu, China
Xiong Fu-rui
Nuclear Power Institute of China, Chengdu, China
Paper No:
PVP2017-65207, V004T04A029; 9 pages
Published Online:
October 26, 2017
Citation
Nai-bin, J, Li-xia, G, Xuan, H, Feng-gang, Z, & Fu-rui, X. "Research on Two-Phase Flow Induced Vibration Characteristics of U-Tube Bundles." Proceedings of the ASME 2017 Pressure Vessels and Piping Conference. Volume 4: Fluid-Structure Interaction. Waikoloa, Hawaii, USA. July 16–20, 2017. V004T04A029. ASME. https://doi.org/10.1115/PVP2017-65207
Download citation file:
32
Views
Related Proceedings Papers
Related Articles
Mechanics of Pipes Conveying Fluids—Part II: Applications and Fluidelastic Problems
J. Pressure Vessel Technol (April,2011)
Experimental and Numerical Characterization of Flow-Induced Vibration of Multispan U-tubes
J. Pressure Vessel Technol (February,2012)
Vibration of a Normal Triangular Tube Bundle Subjected to Two-Phase Freon Cross Flow
J. Pressure Vessel Technol (October,2009)
Related Chapters
Random Turbulence Excitation in Single-Phase Flow
Flow-Induced Vibration Handbook for Nuclear and Process Equipment
Fluidelastic Instability of Tube Bundles in Single-Phase Flow
Flow-Induced Vibration Handbook for Nuclear and Process Equipment
Hydrodynamic Mass, Natural Frequencies and Mode Shapes
Flow-Induced Vibration Handbook for Nuclear and Process Equipment