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http://dx.doi.org/10.9725/kstle.2007.23.3.130

Fretting Wear Characteristics of the Corroded Fuel Cladding Tubes for Nuclear Fuel Rod against Supporting Girds  

Kim, Jin-Seon (School of Mechanical Engineering, SunKyunKwan University)
Park, Se-Min (School of Mechanical Engineering, SunKyunKwan University)
Kim, Yong-Hwan (Fuel Technology Center, Korea Nuclear Fuel Co.)
Lee, Seung-Jae (Fuel Technology Center, Korea Nuclear Fuel Co.)
Lee, Young-Ze (School of Mechanical Engineering, SunKyunKwan University)
Publication Information
Tribology and Lubricants / v.23, no.3, 2007 , pp. 130-133 More about this Journal
Abstract
Fuel cladding tubes in nuclear fuel assembly are held up by supporting grids 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 and support. The fretting wear of tube and support can threaten the safety of nuclear power plant. Therefore, a research about the fretting wear characteristics of tube-support is required. The fretting wear tests were performed with supporting grids and cladding tubes, especially after corrosion treatment on tubes, in water. The tests were done using various applied loads with fixed amplitude. 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. Due to stick phenomena the wear depth was changed as increasing load and temperature. The maximum wear depth was decreased as increasing the water temperatures. At high temperatures there are the regions of some severe adhesion due to stick phenomena.
Keywords
corroded fuel cladding tube; fretting wear; supporting grid; wear coefficient; wear depth;
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  • Reference
1 핵기계공학, pp. 9-29, 한국원자력학회, 1989
2 Dong-Goo Kim and Young-Ze Lee, Experimental investigation on sliding and fretting wear of steam generator tube materials, Wear, Vol. 250, pp. 673-680, 2001   DOI   ScienceOn
3 C. Phalippou et al, The Predictive Analysis of Wear Work-rates in Wear test Rigs, Journal of Pressure Vessel Piping, 328, 1996
4 S.H. Jeong, C.Y.Park, Y.Z.Lee, Key Engineering Materials, Vol. 293-300, pp. 1412-1417, 2005
5 Sung-Hoon Jeong and Young-Ze Lee, Wear Characteristics of Inconel 690 and Inconel 600 in Elevated Temperture, Key Engineering Materials, Vol. 297, pp. 1424-1429, 2005   DOI
6 P.E. MacDonald, V.N. Shah,et al, Report NUREG/CR-6365, 1-77, 1996
7 S.C. Kang, M.H. Song, et ai, Report KINS/AR-669, pp. 5-37, 1999