Sliding wear behaviors of steam generator tubes in various environments

被引:0
|
作者
Kim, Gyung Guk [1 ]
Noh, Seung Dae
Park, Gi Sung
Kim, Seon Jin
Lee, Deok Hyun
Hur, Do Haeng
Choi, Myung Sik
Han, Jung Ho
机构
[1] Hanyang Univ, Div Mat Sci & Engn, Seoul 133791, South Korea
[2] Korea Atom Energy Res Inst, Taejon 305353, South Korea
来源
关键词
steam generator tubes; sliding wear; glaze layer;
D O I
10.4028/www.scientific.net/MSF.510-511.566
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Wear damage of steam generator tubes for nuclear power plants can cause the leakage of radioactive substances. Therefore, the evaluation of integrity and safety for tubes is very important from the viewpoint of nuclear ecocide. In the present study, to investigate the wear properties of Inconel 600 and 690 steam generator tube materials mated with 409 stainless steel commonly used as support plate, sliding wear tests were performed with increasing sliding distance in air and in elevated temperature water environment, respectively. The wear volume of tube materials was less than those of supports under all conditions. There were no significant differences in the wear behavior for the Inconel 600 and 690 tubes, independently of the testing environment.
引用
收藏
页码:566 / 569
页数:4
相关论文
共 50 条
  • [21] Wear transitions of tube-support materials for a nuclear steam generator through sliding wear test and fretting wear test
    Jeong, Sung-Hoon
    Lee, Byoung-Jong
    Lee, Young-Ze
    ADVANCED NONDESTRUCTIVE EVALUATION I, PTS 1 AND 2, PROCEEDINGS, 2006, 321-323 : 430 - 433
  • [22] Simulation of eddy current testing of steam generator tubes with wear and secondary side magnetite deposits
    Sollier, T.
    Decitre, J.-M.
    Vigneron, A.
    Demaldent, E.
    Insight: Non-Destructive Testing and Condition Monitoring, 2022, 64 (02): : 73 - 78
  • [23] Effects of Wear on Stress Corrosion Cracking Initiation Behavior of Alloy 690 Steam Generator Tubes
    Jinna, Mei
    Yaolei, Han
    Qunjia, Peng
    Zhen, Cai
    Peng, Wang
    Wenxin, Ti
    Xiyou Jinshu Cailiao Yu Gongcheng/Rare Metal Materials and Engineering, 2022, 51 (10): : 3547 - 3553
  • [24] Effects of Wear on Stress Corrosion Cracking Initiation Behavior of Alloy 690 Steam Generator Tubes
    Mei, Jinna
    Han, Yaolei
    Peng, Qunjia
    Cai, Zhen
    Wang, Peng
    Ti, Wenxin
    RARE METAL MATERIALS AND ENGINEERING, 2022, 51 (10) : 3547 - 3553
  • [25] Simulation of eddy current testing of steam generator tubes with wear and secondary side magnetite deposits
    Sollier, T.
    Decitre, J-M
    Vigneron, A.
    Demaldent, E.
    INSIGHT, 2022, 64 (02) : 73 - 78
  • [26] Flow-induced vibration and fretting-wear predictions of steam generator helical tubes
    Jo, Jong Chull
    Jhung, Myung Jo
    NUCLEAR ENGINEERING AND DESIGN, 2008, 238 (04) : 890 - 903
  • [27] Dynamic non-linear analysis for the fretting wear prediction in steam generator heating tubes
    Schramm, Konrad
    Bergholz, Steffen
    American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP, 2000, 414 : 179 - 185
  • [28] EXPERIMENTAL CHARACTERIZATION OF SLIDING AND IMPACT FRICTION COEFFICIENTS BETWEEN STEAM-GENERATOR TUBES AND AVB SUPPORTS
    HASLINGER, KH
    STEININGER, DA
    JOURNAL OF SOUND AND VIBRATION, 1995, 181 (05) : 851 - 871
  • [29] ELECTROCHEMICAL DECONTAMINATION OF STEAM-GENERATOR TUBES
    OPERSCHALL, H
    ATOMKERNENERGIE-KERNTECHNIK, 1985, 47 (01): : 27 - 29
  • [30] Reliability of steam generator tubes with axial cracks
    Cizelj, L
    Mavko, B
    Vencelj, P
    JOURNAL OF PRESSURE VESSEL TECHNOLOGY-TRANSACTIONS OF THE ASME, 1996, 118 (04): : 441 - 446