Fretting Wear Characteristics of Nuclear Fuel Cladding in High-Temperature Pressurized Water

Fretting Wear Characteristics of Nuclear Fuel Cladding in High-Temperature Pressurized Water

Abstract In pressurized water reactor (PWR), fretting wear is one of the main causes of fuel assembly failure. Moreover, the operation condition of cladding is complex and harsh. A unique fretting damage test equipment was developed and tested to simulate the fretting damage evolution process of cla...

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Bibliographic Details
Main Authors: Jun Wang, Haojie Li, Zhengyang Li, Yujie Lei, Quanyao Ren, Yongjun Jiao, Zhenbing Cai
Format: Article
Language:English
Published: SpringerOpen 2023-09-01
Series:Chinese Journal of Mechanical Engineering
Subjects:
Fretting wear
Cladding
High temperature and high pressure
Zirconium alloy
Online Access:https://doi.org/10.1186/s10033-023-00931-4

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