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Flow-Induced Vibration Test in the Preheater Region of a Steam Generator Tube Bundle
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  • Flow-Induced Vibration Test in the Preheater Region of a Steam Generator Tube Bundle
  • Flow-Induced Vibration Test in the Preheater Region of a Steam Generator Tube Bundle
저자명
Kim. Beom-Shig,Hwang. Jong-Keun
간행물명
Journal of the Korean Nuclear Society
권/호정보
1997년|29권 1호|pp.85-91 (7 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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기타
이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

Cross-flow existing in a shell-and-tube steam generator can cause a tube to vibrate. There are four regions subjected to cross-flow in Yonggwang units 3 and 4 (YGN 3 and 4) steam generators, which are of the same design as the steam generators for Palo Verde nuclear power plant Palo Verde units 1 and 2 steam generators have experienced localized oar at the comers of the cold side recirculating fluid inlet regions. A number of design modifications were made to preclude tube failure in specific regions of YGN 3 and 4 steam generators. Therefore, flow induced vibration experiments were done to determine the vibration magnitude of tubes in the economizer tube free lane region. The objective of this experiment is to demonstrate that the tube displacement is less than 0.01 inch rms at 100% of full power flow and to quantify the remaining design margin at 120ft and 140% of full power flow.