Proceedings of the Korean Society of Tribologists and Lubrication Engineers Conference (한국윤활학회:학술대회논문집)

Korean Tribology Society (한국트라이볼로지학회)
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Fretting Wear Characteristics of Nuclear Fuel Rod Material

핵연료봉재의 프레팅 마멸 특성

  • 김태형 (경북대학교 대학원 기계공학과) ;
  • 조광희 (한국원자력연구소) ;
  • 김석삼 (경북대학교 기계공학과)
  • Published : 1996.04.01
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Abstract

The fretting wear characteristics for Zircaloy-4 tube used as fuel rod in the nuclear power plant have been investigated. The fretting wear tester was designed and manufactured for this experiment. This study was focused on main factors of fretting wear, cycle, slip amplitude and normal load. The worn surfaces were observed by SEM.

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