Flow-Induced Vibration Analysis for the Secondary Support Assembly of Reactor Internal

Zhang Kefeng;xie yong cheng

Journal of Vibration and Shock ›› 2009, Vol. 28 ›› Issue (12) : 183-187.

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PDF(1679 KB)
Journal of Vibration and Shock ›› 2009, Vol. 28 ›› Issue (12) : 183-187.
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Flow-Induced Vibration Analysis for the Secondary Support Assembly of Reactor Internal

  • Zhang Kefeng;xie yong cheng
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Abstract

The secondary support assembly of reactor internals, which is located below the lower support plate, is an important part of the lower internals and is subjected to flow-induced loads. So flow-induced vibration (FIV) analysis is required to be performed so as to ensure the structural integrity of the secondary support assembly. In this paper, Influences of various flow excitation mechanisms such as random turbulence, quasi-static turbulence, vortex shedding, core barrel motion, etc. on FIV response of the secondary support assembly of 300MWe nuclear reactor internals are studied. Structural dynamic loads caused by FIV are calculated by means of combinating dynamic responses resulting from various excitation mechanics via square root of sum of squares (SRSS) method, which provides basis for stress analysis and evaluation of the secondary support assembly.

Key words

secondary support assembly / flow-induced vibration / random turbulence / quasi-static turbulence / vortex shedding / core barrel motion

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Zhang Kefeng;xie yong cheng. Flow-Induced Vibration Analysis for the Secondary Support Assembly of Reactor Internal[J]. Journal of Vibration and Shock, 2009, 28(12): 183-187
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