Flow-induced vibrations (FIV) continue to affect the operations of nuclear power plant components such as heat exchanger tube bundles. The negative effect of FIV is in the form of tube fatigue, cracking, and fretting wear at the supports. Fretting wear at the supports is the result of tube/support impact and friction. Fluidelastic and turbulence forces are the two main excitation mechanisms that feed energy into the system causing these violent vibrations. To minimize this effect all support clearances must be kept at a very small value. This paper investigates the consequences of losing the effectiveness of a particular support as a result of corrosion or excessive fretting wear. A full U-bend tube subjected to both fluidelastic and turbulence forces is utilized in this work. The performance of countermeasures such as the installation of additional flat bars in the U-bend region is thoroughly investigated. The investigation utilized both deterministic and probabilistic techniques.
Evaluation of the Integrity of Steam Generator Tubes Subjected to Flow Induced Vibrations
Contributed by the Pressure Vessel and Piping Division of ASME for publication in the JOURNAL OF PRESSURE VESSEL TECHNOLOGY. Manuscript received August 29, 2013; final manuscript received February 13, 2014; published online August 19, 2014. Assoc. Editor: Samir Ziada.
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Hassan, M., and Riznic, J. (August 19, 2014). "Evaluation of the Integrity of Steam Generator Tubes Subjected to Flow Induced Vibrations." ASME. J. Pressure Vessel Technol. October 2014; 136(5): 051301. https://doi.org/10.1115/1.4026982
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