Flow-induced vibration and fluid-structure interaction in nuclear power plant components

• Published in: Journal of wind engineering and industrial aerodynamics Vol. 33; no. 1; pp. 405 - 418
• Main Author: Fujita, K.
• Format: Journal Article
• Language: English
• Published: Elsevier Ltd 01.03.1990
• Subjects: Cross flow; fluid mechanics; fluid-structure interaction; leak detection; leakage flow; nuclear power plant; parallel flow; sloshing; vibration; sloshing; parallel flow; leakage flow; nuclear power plant; fluid-structure interaction; Cross flow
• ISSN: 0167-6105; 1872-8197
• DOI: 10.1016/0167-6105(90)90056-I

This paper gives some subjects of flow-induced vibration (FIV) and fluid-structure interaction (FSI) in nuclear power plant components, especially based on a pressurized water reactor (PWR), a type of light water reactor, and a fast breeder reactor (FBR), promoted as a national project, both of which the author has been experienced with. The flow-induced vibration discussed in this paper also covers cross flow-induced periodic wake shedding, fluid elastic instability and axial flow-induced damping observed in the fuel assembly inside the reactor core, the tube bundle of the steam generator and other components of the reactor, as well as leakage flow-induced vibration. In addition, the discussion on the flow-induced vibration in extended to two-phase flow induced fluid-elastic vibration, random excitation and resultant fretting wear in the U-bend tube bundle of the steam generator, as well as to the problem of vibration induced by fluid pulsation in the component-connecting piping coupled with mechanical vibration of the piping. On the other hand, the fluid-structure interaction discussed here covers hydrodynamic mass-effect, added damping in very closely space reactor internals, as well as sloshing of the free surface of liquid sodium in FBR.