Proceedings of the Korean Society of Tribologists and Lubrication Engineers Conference (한국윤활학회:학술대회논문집)
- 2003.11a
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- Pages.313-323
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- 2003
Evaluation of spring shape effect on the nuclear fuel fretting using worn area
핵연료 프레팅 마멸에서 마멸면적을 이용한 스프링 형상 영향 평가
- Lee Young-Ho (Korea Atomic Energy Research Institute) ;
- Kim Hyung-Kyu (Korea Atomic Energy Research Institute) ;
- Jung Youn-Ho (Korea Atomic Energy Research Institute)
- Published : 2003.11.01
Abstract
The sliding wear behaviors of Zircaloy-4 nuclear fuel rod were investigated using two support springs with convex and concave shapes in room temperature air and water. The main focus is to compare the wear behavior of various test variables such as slip amplitude, environment, contact contours with different spring shape and a number of cycles. The results indicated that wear volume and maximum wear depth increased with slip amplitude in both air and water, but their trends tended to change according to the spring shapes and test environments. In air condition, the wear volume was controlled by wear debris behavior generated on worn surface. As a result, final wear volume and maximum wear depth decreased if a ratio of protruded wear volume to worn area