Flow Induced Vibration of Reactor Internals Structure : Analysis and Experiment

원자로 내부구조물의 유체흐름에 의한 진동 - 해석 및 실험

  • 이희남 (한국원자력연구소 원자로개발그룹) ;
  • 최순 (한국원자력연구소 원자로개발그룹) ;
  • 김태형 (한국원자력연구소 원자로개발그룹) ;
  • 황종근 (한국원자력연구소 원자로개발그룹) ;
  • 김정규 (한국원자력연구소 원자로개발그룹)
  • Published : 1995.10.01

Abstract

A series of vibration assessment programs has been performed for Yonggwang Nuclear Power Plant Unit 4 (YGN 4) in order to verify the structural integrity of the reactor internals for flow induced vibration prior to its commercial operation. The structural analysis was done to provide the basis for measurement and the theoretical evidence for the structural integrity of the reactor internals. The actual flow induced hydraulic loads and reactor internals vibration response data were measured and recorded during pre-core hot functional testing of the plant. Then, the measured data have been reduced and analyzed, and compared with the analysis results such as the frequency contents, stresses, strains and displacements. It is concluded that the structural analysis methodology performed for vibration response of the reactor internals due to the flow induced vibration is appropriately conservative, and also that the structural integrity of YGN 4 reactor internals to flow induced vibration is acceptable for long term operation.

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