Study on Tangential Fretting Wear Behavior of Zirconium Alloy Cladding at High Temperature

Ren Quan yao; Pu Zeng ping; Jiao Yongjun; Zheng Meiyin; Chen Ping; Han Yuanji; Liu Menglong; Zhuang Wenhua; Guo Xianglong; Zhang Lefu

doi:10.13832/j.jnpe.2022.S2.0082

Volume 43 Issue S2

Dec. 2022

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Article Navigation > Nuclear Power Engineering > 2022 > 43(S2): 82-87

Ren Quan yao, Pu Zeng ping, Jiao Yongjun, Zheng Meiyin, Chen Ping, Han Yuanji, Liu Menglong, Zhuang Wenhua, Guo Xianglong, Zhang Lefu. Study on Tangential Fretting Wear Behavior of Zirconium Alloy Cladding at High Temperature[J]. Nuclear Power Engineering, 2022, 43(S2): 82-87. doi: 10.13832/j.jnpe.2022.S2.0082

Citation:

Ren Quan yao, Pu Zeng ping, Jiao Yongjun, Zheng Meiyin, Chen Ping, Han Yuanji, Liu Menglong, Zhuang Wenhua, Guo Xianglong, Zhang Lefu. Study on Tangential Fretting Wear Behavior of Zirconium Alloy Cladding at High Temperature[J]. Nuclear Power Engineering, 2022, 43(S2): 82-87. doi: 10.13832/j.jnpe.2022.S2.0082

Citation:

Ren Quan yao, Pu Zeng ping, Jiao Yongjun, Zheng Meiyin, Chen Ping, Han Yuanji, Liu Menglong, Zhuang Wenhua, Guo Xianglong, Zhang Lefu. Study on Tangential Fretting Wear Behavior of Zirconium Alloy Cladding at High Temperature[J]. Nuclear Power Engineering, 2022, 43(S2): 82-87. doi: 10.13832/j.jnpe.2022.S2.0082

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Study on Tangential Fretting Wear Behavior of Zirconium Alloy Cladding at High Temperature

doi: 10.13832/j.jnpe.2022.S2.0082

1.
Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu, 610213, China
2.
Department of Nuclear Science and Engineering, Shanghai Jiaotong University, Shanghai, 200240, China

Received Date: 2022-06-30
Rev Recd Date: 2022-08-26
Publish Date: 2022-12-31

Abstract

Abstract

During the service of the nuclear fuel assembly, the fretting wear between the grid spacer holding structure and the fuel rod is the first major factor leading to the damage of the fuel rod cladding, accounting for about 54.8% of the fuel rod cladding failure. According to the tangential fretting wear behavior of zirconium alloy cladding tubes with different holding structures, the experimental study on wear under high temperature and high pressure hydrochemical environment is carried out. The key parameters, such as cladding tube wear scar morphology, wear volume and wear depth of curved and planar holding structures under different holding forces are compared and analyzed. The results show that the wear of the curved holding structure on the fuel rod cladding is mainly abrasive wear, lamellar shedding and “ploughing” effect, while the planar structure is dominated by “ploughing” effect and lamellar shedding, and the abrasive wear is less. In addition, under the same conditions, the maximum wear depth of the curved holding structure is larger than that of the planar holding structure.
- Tangential fretting wear,
- Holding structure,
- Zirconium alloy cladding,
- Wear scar

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References(18)

References

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