FLOW-INDUCED VIBRATION AND FLUID STRUCTURE INTERACTION IN NUCLEAR-POWER-PLANT COMPONENTS

被引:17
|
作者
FUJITA, K
机构
[1] Vibration and Noise Control Laboratory, Takasago Research and Development Center, Mitsubishi Heavy Industries, Ltd., Takasago, Hyogo Pref.
关键词
Cross flow; fluid-structure interaction; leakage flow; nuclear power plant; parallel flow; sloshing;
D O I
10.1016/0167-6105(90)90056-I
中图分类号
TU [建筑科学];
学科分类号
0813 ;
摘要
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. © 1990.
引用
收藏
页码:405 / 418
页数:14
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