Fretting Wear Behavior of Cr Coated Zr-1Nb Alloy Cladding in High Temperature and High Pressure Water

被引:1
作者
Liao, Yehong [1 ]
Dai, Gongying [2 ,3 ]
Yan, Jun [1 ]
Lin, Xiaodong [3 ]
Peng, Zhenxun [1 ]
Liang, Xue [3 ]
Li, Yifeng [3 ]
Xue, Jiaxiang [1 ]
Li, Qiang [3 ]
机构
[1] China Nucl Power Technol Res Inst Co Ltd, Nucl Fuel & Mat Dept, Shenzhen 518026, Peoples R China
[2] Shanghai Univ, Inst Mat, Shanghai 200072, Peoples R China
[3] Shanghai Univ, Instrumental Anal & Res Ctr, Shanghai 200444, Peoples R China
关键词
nuclear fuel cladding; Cr-coated zirconium alloy; high temperature and high pressure water; fretting wear; grinding pair; ACCIDENT-TOLERANT FUEL; RESEARCH PROGRESS; ZIRCONIUM ALLOY; CORROSION; STEEL;
D O I
10.12442/j.issn.1002-185X.20230530
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
The fretting wear behaviors of Cr-coated Zr-1Nb cladding tube with different griding pairs in simulated pressurized water reactor primary water environment at 290 and 310 degrees C were studied by three-dimensional optical surface profilometer, scanning electron microscope, electron backscattered diffraction and energy spectrometer. The results show that the fretting wear behaviors between the Cr-coated Zr-1Nb cladding and griding pairs (i.e., Zr-4 dimple or Inconel 718 spring) are both dominated by the adhesive wear mechanism, accompanied by material transfer from the grinding pair to the Cr-coated cladding. With the increase in temperature, the fretting wear resistance of the Cr-coated cladding is decreased, as manifested by increased surface wear depth and volume. However, the fretting wear mechanism still remains unchanged within the temperature range tested in this work. In addition, the wear degree of the Cr-coated cladding with Zr-4 dimple is greater than that with Inconel 718 spring, which is related to the hardness and contact mode of the grinding pair.
引用
收藏
页码:2843 / 2851
页数:9
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