Page 134 - 《摩擦学学报》2021年第3期

第 41 卷 第 3 期 摩 擦 学 学 报 Vol 41 No 3
2021 年 5 月 Tribology May, 2021

DOI: 10.16078/j.tribology.2020222

核反应堆中锆合金包壳及其表面涂层的

微动磨损行为研究进展

1,2
1
1,2
江海霞 , 段泽文 , 马鹏翔 , 王 鹏 1*
(1. 中国科学院兰州化学物理研究所 固体润滑国家重点实验室，甘肃 兰州 730000;
2. 中国科学院 中科院大学，北京 100049)
摘 要: 包壳的微动磨损是世界压水堆燃料失效的主要原因，因此理解核反应堆中燃料包壳微动磨损行为对核反应
堆安全运行至关重要. 服役于核裂变堆一回路的锆合金包壳，不但承受着堆内高温高压冷却剂的冲刷，还面临腐
蚀、强中子辐照的苛刻环境. 本文作者从机械因素、水工条件、辐照和腐蚀几个方面总结了反应堆中服役环境对包
壳微动摩擦行为的影响，并阐述了事故容错燃料(ATF)包壳涂层的研究进展及其对格-棒间微动磨损的影响. 最后对
核反应堆包壳的微动磨损、腐蚀磨损未来的研究方向进行了展望.
关键词: 包壳材料; 事故容错燃料包壳涂层; 辐照; 微动磨损; 腐蚀磨损
中图分类号: TL364+.9 文献标志码: A 文章编号: 1004-0595(2021)03–0423–14

Research Progress on Fretting Wear Behavior of Fuel
Cladding Materials in Nuclear Reactor

1,2 1,2 1 1*
JIANG Haixia , DUAN Zewen , MA Pengxiang , WANG Peng

(1. State Key Laboratory of Solid Lubrication, Lanzhou Institute of Chemical Physics, Chinese Academy of Sciences,
Gansu Lanzhou 730000, China
2. University of Chinese Academy of Sciences, Beijing 100049, China)
Abstract: Fretting wear failure of cladding is the main cause of fuel failure of pressurized water reactor in the world,
thus understanding the fretting wear behavior of fuel cladding in nuclear reactor is very important to the safe operation
of nuclear reactor. The zirconium alloy cladding used in the primary circuit of nuclear fission reactor not only bears the
erosion of high temperature and high pressure coolant, but also faces the harsh environment such as corrosion, strong
irradiation. This paper summarizes the influence of service environment on fretting wear behavior of cladding from the
aspects of mechanical factors, hydraulic conditions, irradiation and corrosion, and expounds the research progress of
accident-tolerant zirconium alloy cladding coating material and its influence on fretting wear between grid to rod fretting
in the future. Finally, the future research direction of fretting wear and corrosion wear of nuclear reactor cladding is
prospected.
Key words: cladding material; accident tolerant fuel cladding coating; irradiation; fretting wear; corrosive wear

[1]
随着不可再生能源的不断消耗及环境污染的加 电发电量也在逐年增加[图1(a)] . 目前，世界上主要
剧，低碳、高效的核能受到人们的广泛关注. 截至 使用的是第二代核电技术，主要反应堆型为压水堆和
[2]
2019年底，我国核电总装机容量位于全球第三位，核 沸水堆 . 核电站主要利用铀燃料进行核分裂连锁反

Received 20 October 2020, revised 26 November 2020, accepted 7 December 2020, available online 28 May 2021.
*Corresponding author. E-mail: pengwang@licp.cas.cn, Tel: +86-931-4968144.
The project was supported by CAS “Light of West China” Program and National Natural Science Foundation of China (52005483).
西部之光交叉团队和青年科学基金项目(52005483)资助.