Investigation on Corrosion Model of Cr-coated Zirconium Alloy Cladding

被引：0
|
作者：
Shen, Yong [1 ,2 ]
Zeng, Xiehu [1 ,2 ]
Duan, Zhengang [1 ,2 ,3 ]
Wen, Qinglong [1 ,2 ,3 ]
Yuan, Bo [1 ,2 ]
He, Liang [4 ]
Gao, Shixin [4 ]
机构：
[1] School of Energy and Power Engineering, Chongqing University, Chongqing,400044, China
[2] Liangjiang Laboratory for New Energy (Nuclear Energy and Power), Chongqing,400044, China
[3] Key Laboratory of Low-grade Energy Utilization Technologies and Systems, Ministry of Education, Chongqing University, Chongqing,400044, China
[4] Science and Technology on Reactor System Design Technology Laboratory, Nuclear Power Institute of China, Chengdu,610213, China
来源：
Hedongli Gongcheng/Nuclear Power Engineering | 2024年 / 45卷
关键词：
Corrosion rate - Corrosion resistant alloys - Corrosion resistant coatings - Corrosive effects - Lead alloys - Metal cladding - Nuclear energy - Nuclear reactor accidents - Oxidation resistance - Zirconium alloys;
D O I：
10.13832/j.jnpe.2024.S1.0175
中图分类号：
学科分类号：
摘要：
As one of the candidate materials for accident tolerant fuel (ATF) cladding, Cr coating can significantly improve the corrosion resistance and oxidation resistance of zirconium alloy cladding, which is expected to prolong the service life. In order to evaluate the corrosion and oxidation behavior of Cr-coated zirconium alloy cladding, a corrosion model of Cr-coated zirconium alloy cladding under normal operating conditions of PWR was established in this paper, and the model was verified based on the experimental data in the literature. Based on this model, the effects of heat flux and mass flow rate on the corrosion of Cr-coated zirconium alloy cladding were analyzed. The results show that the corrosion thickness increases with the increase of heat flux. In addition, the increase of coolant mass flow rate leads to the decrease of cladding wall temperature, which eventually leads to the decrease of cladding corrosion thickness. © 2024 Atomic Energy Press. All rights reserved.
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页码：175 / 180
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