http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
온도 상승이 개량형 핵연료 피복관과 지지격자 사이의 프레팅 마멸에 미치는 영향
박용창(Yong-Chang Park),정성훈(Sung-Hoon Jeong),김진선(Jin-Seon Kim),김용환(Yong-Hwan Kim),이영제(Young-Ze Lee) 한국트라이볼로지학회 2006 한국윤활학회지(윤활학회지) Vol.22 No.3
The experimental investigation was performed to find the associated changes in characteristics of fretting wear with various water temperatures. The fretting wear tests were carried out using the zirconium alloy tubes and the grids with increasing the water temperature. The tube materials in water of 20℃, 50℃ and 80℃ were tested with the applied load of 20 N and the relative amplitude of 200 ㎛. The worn surfaces were observed by SEM, EDX analysis and 2D surface profiler. As the water temperature increased, the wear volume was decreased, but oxide layer was increased on the worn surface. The abrasive wear mechanism was observed at water temperature of 20℃ and adhesive wear mechanism occurred at water temperature of 50℃, 80℃. As the water temperature increased, surface micro-hardness was decreased, but wear depth and wear width were decreased due to increasing stick phenomenon. Stick regime occurred due to the formation of oxide layer on the worn surface with increasing water temperatures.
박용창(Young-Chang Park),이중희(Jung-Hee Lee),이규선(Gyu-Sun Lee),김용환(Yong-Hwan Kim),이성재(Seung-Jae Lee),이영제(Young-Ze Lee) 한국트라이볼로지학회 2006 한국트라이볼로지학회 학술대회 Vol.2006 No.6
Fretting can be defined as the oscillatory motion with very small amplitudes, which usually occur between two contacting surfaces. Fretting wear is the removal of material from contacting surfaces through fretting action. This fretting wear, which occurs between cladding tubes of nuclear fuel rod and grids, causes in damages the cladding tubes by flow induced vibration in a nuclear reactor. In this paper the fretting wear tests were performed with two types of cladding tubes and three types of supporting grids in water. Fretting wear tests were done using various applied loads. From the results of fretting tests, the wear amounts of tube materials can be predictable by obtaining the wear coefficient using the work rate model. Depending on various normal load, tube materials, and supporting grid shapes, distinctively different wear scar of fretting and stick-slip mechanism can occur.
인코넬 690과 600의 스틱-슬립에 따른 마멸 메커니즘 규명
정성훈(Sung-Hoon Jeong),이병종(Byoung-Jong Lee),박용창(Yong-Chang Park),이영제(Young-Ze Lee) 한국트라이볼로지학회 2004 한국트라이볼로지학회 학술대회 Vol.38 No.-
Fretting is the small-amplitude oscillatory motion between two solid surfaces in contact. Fretting wear is the removal of material from contacting surfaces through fretting action. Fretting wear of steam generator tube in nuclear power plant is a serious topic in recent years. In this paper fretting wear tests were performed in water at room temperature. Fretting tests were done using Inconel 690 and 600 tubes under various applied loads. From the results of fretting wear tests, we get the fretting wear mechanism for Inconel 690 and 600 tubes due to stick-slip. The wear of tube material can be predicted by obtaining wear coefficient using the work rate model. This paper is useful to evaluate the wear characteristics of Inconel 690 and 600 for nuclear steam generator tubes.