Tribology and Lubricants

  • 제24권6호
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  • Pages.362-367
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  • 2008
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  • 2713-8011(pISSN)
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  • 2713-802X(eISSN)
한국트라이볼로지학회 (Korean Tribology Society)
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이상 유동 환경이 증기 발생기 세관과 지지대의 프레팅 마모에 미치는 영향에 대한 연구

The Influence of Two Phase Flow on Fretting Wear between Steam Generator Tube and Supporting Bar

  • 이영제 (성균관대학교 기계공학부) ;
  • 박정민 (성균관대학교 기계공학부) ;
  • 정성훈 (성균관대학교 기계공학부) ;
  • 김진선 (성균관대학교 기계공학부) ;
  • 박세민 (성균관대학교 기계공학부)
  • Lee, Young-Ze (Dept. of Mechanical Engineering, Sungkyunkawn University) ;
  • Park, Jung-Min (Dept. of Mechanical Engineering, Sungkyunkawn University) ;
  • Jeong, Sung-Hoon (Dept. of Mechanical Engineering, Sungkyunkawn University) ;
  • Kim, Jin-Seon (Dept. of Mechanical Engineering, Sungkyunkawn University) ;
  • Park, Se-Min (Dept. of Mechanical Engineering, Sungkyunkawn University)
  • 발행 : 2008.12.31
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초록

Tubes in nuclear steam generators are held up by supports because the tubes are long and slender. Fluid flows of high-pressure and high-temperature in the tubes cause oscillating motions between tubes and supports. This is called as FIV (flow induced vibration), which causes fretting wear in contact parts of tube-support. The fretting wear of tube-support can threaten the safety of nuclear power plant. The tube and support materials were Inconel 690 and STS 409. The wear tests were conducted in various environments, which are in water without flow, in flowing water and in flowing water with air. The results showed that the flow of water influenced on the wear-life of tube. The wear-life of tube decreased in water flow as compared with wear-life in stationary water.

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참고문헌

  1. C.E Taylor, M.J.Pettigrew et al, 'Vibration Damping in Multispan Heat Exchanger Tubes', Journal of Pressure Vessel Technolohy, Vol. 120, pp. 283-289, 1988
  2. P.L. Ko and H. Basista, 'Correlation of Support Impact Force and Fretting - Wear for a Heat Exchanger Tube', Journal of Pressure Vessel Technology, Vol. 106, pp. 69-77, 1984 https://doi.org/10.1115/1.3264311
  3. D.G. Kim and Y.Z. Lee, 'Expeirmental Investigation on Sliding and Fretting Wear of Steam Generator Tube Matrials', Wear, Vol. 250, pp. 673, 2001 https://doi.org/10.1016/S0043-1648(01)00676-7
  4. S.H. Jeong, B.J. Lee, and Y.Z. Lee, 'Wear Transitions of Tube-Support Materials for a Nuclear Steam Generator Through Sliding Wear Test and Fretting Wear Test', Key Engineering Materials, Vol. 321-323, pp. 430-433, 2006 https://doi.org/10.4028/www.scientific.net/KEM.321-323.430
  5. S.H. Jeong, J.M. Park, J.H. Lee, and Y.Z. Lee, 'Wear Transitions of Tube-Support Components for Nuclear Steam Generator under Fretting Conditions', Key Engineering Materials, Vol. 326-328, pp. 1253-1266, 2006