Evolution of fretting wear characteristics of Cr-coated cladding under high-temperature pressurized water environment

被引:0
|
作者
Wang, Jun [1 ]
Li, Ke [1 ]
Wu, Yuchun [1 ,2 ]
Xie, Yujie [1 ]
Ni, Jing [3 ]
Zhu, Zefei [3 ]
Cai, Zhenbing [1 ]
机构
[1] Southwest Jiaotong Univ, Tribol Res Inst, Key Lab Adv Technol Mat, Chengdu 610031, Peoples R China
[2] Chengdu Holy Grp Ind Co Ltd, Chengdu 610041, Sichuan, Peoples R China
[3] Hangzhou Dianzi Univ, Sch Mech Engn, Hangzhou 310018, Peoples R China
关键词
Fretting wear; Accident-tolerant fuel cladding; High-temperature pressurized water; Cr coating; NUCLEAR-FUEL CLADDINGS; MICRO-ARC OXIDATION; ALLOY; 690; ACCIDENT; BEHAVIOR; ROD; IMPACT; TIME;
D O I
10.1016/j.nucengdes.2024.113665
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The Cr (chromium) based coating is the most simple, studied, and promising coating for the accident-tolerant fuel cladding of pressurized water reactors. In this work, special tangential fretting wear equipment in high- temperature pressurized water was used to carry out experimental research. The influence of cycles on the fretting wear of Cr-coated cladding under high-temperature and high-pressure water environment was investigated, and the evolution characteristic of the coating during the wear process was revealed. The results show that with the increase in cycles, the main wear mechanism of Cr cladding changes from adhesive wear to fatigue wear, and finally to abrasive wear and delamination. Crack caused by fatigue wear during fretting wear was the main factor leading to the failure of the coating. In addition, wear debris accumulated on the surface of the Cr coating during wear and formed a dense friction oxidative layer (glaze layer), so that the Cr coating can maintain a complete structure in the early stage of fretting wear. The shear stress generated by the friction process will accelerate the material removal, and the existence of a friction oxidative layer can play a certain role in lubrication. The two were in a competitive relationship and finally formed a wear cycle mechanism of wear, oxidation, and re-wear.
引用
收藏
页数:19
相关论文
共 50 条
  • [41] High temperature Cr-Zr interaction of two types of Cr-coated Zr alloys in inert gas environment
    Yang, Jianqiao
    Stegmaier, Ulrike
    Tang, Chongchong
    Steinbrueck, Martin
    Grosse, Mirco
    Wang, Shuzhong
    Seifert, Hans Jurgen
    JOURNAL OF NUCLEAR MATERIALS, 2021, 547 (547)
  • [42] Dynamic corrosion properties of impact-fretting wear in high-temperature pure water
    Sato, Y.
    Iwabuchi, A.
    Uchidate, M.
    Yashiro, H.
    WEAR, 2015, 330 : 182 - 192
  • [43] Crud deposition behavior on zirconium alloy fuel cladding in high-temperature pressurized water environments
    Xue, Chaochao
    Mao, Yulong
    Zhang, Ziyu
    Tan, Jibo
    Wu, Xinqiang
    Han, En-Hou
    Ruan, Tianming
    Li, Jinggang
    Liao, Jiapeng
    JOURNAL OF NUCLEAR MATERIALS, 2022, 568
  • [44] FRACTURE-TOUGHNESS EVALUATION OF GRANITE IN HIGH-TEMPERATURE PRESSURIZED WATER ENVIRONMENT
    WADA, C
    SHOJI, T
    TAKAHASHI, H
    BULLETIN OF THE JSME-JAPAN SOCIETY OF MECHANICAL ENGINEERS, 1986, 29 (258): : 4455 - 4456
  • [45] A study of the oxidation of FeCrAl alloy in pressurized water and high-temperature steam environment
    Park, Dong Jun
    Kim, Hyun Gil
    Park, Jeong Yong
    Jung, Yang Il
    Park, Jeong Hwan
    Koo, Yang Hyun
    CORROSION SCIENCE, 2015, 94 : 459 - 465
  • [46] High-Temperature Oxidation of Cr-Coated Resistance Upset Welds Made from E110 Alloy
    Sidelev, Dmitrii
    Ruchkin, Sergey
    Kashkarov, Egor
    COATINGS, 2021, 11 (05)
  • [47] Influence of Ion Treatment of Cr-Coated Zirconium Alloy (E110) on Resistance to High-Temperature Oxidation
    D. V. Sidelev
    K. A. Zinkovskii
    D. A. Ashikhmin
    Journal of Surface Investigation: X-ray, Synchrotron and Neutron Techniques, 2024, 18 (6) : 1451 - 1459
  • [48] The synergy of corrosion and fretting wear process on Inconel 690 in the high temperature high pressure water environment
    Wang, Zihao
    Xu, Jian
    Li, Jie
    Xin, Long
    Lu, Yonghao
    Shoji, Tetsuo
    Takeda, Yoichi
    Otsuka, Yuichi
    Mutoh, Yoshiharu
    JOURNAL OF NUCLEAR MATERIALS, 2018, 502 : 255 - 262
  • [49] High temperature wear characteristics of WC/Co-Cr composite coating by laser cladding
    School of Materials and Energy, Guangdong University of Technology, Guangzhou, China
    Cailiao Rechuli Xuebao, 3 (177-181):
  • [50] High temperature oxidation of cold spray Cr-coated accident tolerant zirconium-alloy cladding with Nb diffusion barrier layer
    Yeom, Hwasung
    Johnson, Greg
    Maier, Benjamin
    Dabney, Tyler
    Sridharan, Kumar
    JOURNAL OF NUCLEAR MATERIALS, 2024, 588