Fretting wear behaviors of Zr-4 alloy under different ions irradiation conditions

被引:15
|
作者
Jiang, Haixia [1 ,2 ]
Duan, Zewen [1 ,2 ]
Zhang, BeiBei [1 ,2 ]
Zhao, Xiaoyu [1 ,2 ]
Wang, Peng [1 ]
机构
[1] Chinese Acad Sci, Lanzhou Inst Chem Phys, State Key Lab Solid Lubricat, Lanzhou 730000, Gansu, Peoples R China
[2] Univ Chinese Acad Sci, Ctr Mat Sci & Optoelect Engn, Beijing 100049, Peoples R China
基金
中国国家自然科学基金;
关键词
Fretting wear; Heavy ions; Irradiation energy; Zr-4; alloy; Damage level; NUCLEAR-FUEL ROD; CRYSTAL-STRUCTURE; HEXAGONAL METALS; ENERGY LOSS; EVOLUTION; FRICTION; DAMAGE;
D O I
10.1016/j.triboint.2020.106553
中图分类号
TH [机械、仪表工业];
学科分类号
0802 ;
摘要
Studying the fretting wear behaviors of Zr-4 alloy under various ions irradiation conditions plays an important role in understanding the fretting damage source of cladding in nuclear reactor. In the study, fretting wear behaviors for Zr-4 alloy under various ions irradiation conditions were summarized as function of irradiation damage level, incident ion energy and ion species. The results demonstrate that increasing incident energy produced partially or completely amorphous phase in Zr-4 alloy. The friction coefficient and wear rate increase linearly with the increase of irradiation dose, but both are saturated at high irradiation dose, which can be attributed to the existence of an adiabatic or instantaneous recombination volume around the defect. Heavy ions irradiation with large mass and radius cause more and denser defects at shallower surface than ions with smaller radius, results in lower friction coefficient but increased the wear depth and wear rate. Conclusively, the friction coefficient and wear rate of Zr-4 alloy increase at the irradiation conditions investigated in this study. The dominant wear mechanism changes from adhesive wear and abrasive wear to fatigue wear and abrasive wear.
引用
收藏
页数:11
相关论文
共 50 条
  • [41] Fretting wear behaviour of Zr alloy cladding tube under partial slip regime with different duration in simulated primary water of PWR
    Zhang, Yusheng
    Ming, Hongliang
    Lai, Jiang
    Li, Yifeng
    Gao, Lixia
    Wang, Jianqiu
    Han, En-Hou
    APPLIED SURFACE SCIENCE, 2022, 605
  • [42] Wear of silicon nitride ceramics under fretting conditions
    Novak, S
    Drazic, G
    Samardzija, Z
    Kalin, M
    Vizintin, J
    MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 1996, 215 (1-2): : 125 - 133
  • [43] Fretting Wear Characteristics of 690TT Alloy Tube Under Gross Slip Conditions
    Tan W.
    Tian C.
    Tianjin Daxue Xuebao (Ziran Kexue yu Gongcheng Jishu Ban)/Journal of Tianjin University Science and Technology, 2022, 55 (09): : 895 - 902
  • [44] Experimental study of the fretting wear behavior of Inconel 690 alloy under alternating load conditions
    Zhang, Xiao-Yu
    Cai, Zhen-Bing
    Peng, Jin-Fang
    Liu, Jian-Hua
    Zhu, Min-Hao
    Du, Run
    Yuan, Xin-Lu
    Ren, Ping-Di
    PROCEEDINGS OF THE INSTITUTION OF MECHANICAL ENGINEERS PART J-JOURNAL OF ENGINEERING TRIBOLOGY, 2018, 232 (11) : 1343 - 1351
  • [45] Wear of silicon nitride ceramics under fretting conditions
    Novak, S.
    Drazic, G.
    Samardzija, Z.
    Kalin, M.
    Vizintin, J.
    Materials Science and Engineering A, 1996, A215 (1-2): : 125 - 133
  • [46] Low temperature hydrogen embrittlement behavior of Zr-4 alloy
    Xiong, YF
    Li, LF
    Wang, WH
    Zhao, LZ
    Rong, LJ
    ADVANCES IN CRYOGENIC ENGINEERING, VOLS 48A AND B, 2002, 614 : 71 - 75
  • [47] Effect of β-Quenching Treatment on Oxidation Behavior of Zr-4 Alloy
    Kang, Kaiwen
    Zhu, Wencan
    Zhang, Jihao
    Wang, Lesen
    Guo, Defeng
    JOURNAL OF MATERIALS ENGINEERING AND PERFORMANCE, 2024, 34 (6) : 5374 - 5380
  • [48] Corrosion and Wear Properties of Cr Coating and ZrO2/Cr Bilayer Coating on Zr-4 Alloy
    Pan, Xiaolong
    Qiu, Longshi
    Hu, Xiaogang
    Jiang, Haixia
    COATINGS, 2022, 12 (09)
  • [49] Strain fatigue and life estimate of Zr-4 alloy slice
    Cai, Lixun
    Ye, Yuming
    Gao, Qing
    Li, Cong
    Hsi-An Chiao Tung Ta Hsueh/Journal of Xi'an Jiaotong University, 2004, 38 (01): : 97 - 100
  • [50] Hot deformation behavior and processing map of Zr-4 alloy
    Liu, Jianjun
    Wang, Kelu
    Lu, Shiqiang
    Gao, Xiayun
    Li, Xin
    Zhou, Feng
    JOURNAL OF NUCLEAR MATERIALS, 2020, 531