A Study on the Sliding/Impact Wear of a Nuclear Fuel Rod in Room Temperature Air:(I) Development of a Test Rig and Characteristic Analysis

상온 핵연료봉 미끄럼/충격 마멸특성연구:(I) 장치개발 및 특성분석

  • 이영호 (한국원자력연구원 선진경수로연료개발센터) ;
  • 이강희 (한국원자력연구원 선진경수로연료개발센터) ;
  • 김형규 (한국원자력연구원 선진경수로연료개발센터)
  • Published : 2007.05.30

Abstract

A new type of a fretting wear tester has been designed and developed in order to simulate the actual vibration behavior of a nuclear fuel rod for springs/dimples in room temperature. When considering the actual contact condition between fuel rod and spring/dimple, if fretting wear progress due to the flow-induced vibration (FIV) under a specific normal load exerted on the fuel rod by the elastic deformation of the spring, the contacting force between the fuel rod and dimple that were located in the opposite side should be decreased. Consequently, the evaluation of developed spacer grids against fretting wear damage should be performed with the results of a cell unit experiments because the contacting force is one of the most important variables that influence to the fretting wear mechanism. Therefore, it is necessary to develop a new type of fretting test rig in order to simulate the actual contact condition. In this paper, the development procedure of a new fretting wear tester and its performance were discussed in detail.

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