Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water

被引：0
|
作者：
Ping Deng [1 ,2 ]
En-Hou Han [1 ]
Qunjia Peng [1 ,3 ]
Chen Sun [4 ]
机构：
[1] CAS Key Laboratory of Nuclear Materials and Safety Assessment,Institute of Metal Research,Chinese Academy of Sciences
[2] State Power Investment Corporation Research Institute
[3] Nuclear Power Institute of China
[4] Suzhou Nuclear Power Research Institute
来源：
Acta Metallurgica Sinica(English Letters) | 2021年 / 34卷 / 02期
基金：
对外科技合作项目（国际科技项目）;
关键词：
D O I：
暂无
中图分类号：
TG172.1 [辐射腐蚀];
学科分类号：
摘要：
Corrosion behavior and mechanism of irradiated 304 nuclear grade stainless steel were studied in simulated pressurized water reactor primary water. The microstructure of the oxide formed on the steel irradiated to different doses over an exposure period range of 25–1500 h was analyzed and compared. It was found that the general and intergranular corrosion rates of the steel were increased with irradiation dose, in correspondence with an evolution of the general oxide and the oxide formed at the grain boundary. Correlation of the oxide evolution with the corrosion kinetics and mechanism has been discussed in detail.
引用
收藏
页码：174 / 186
页数：13
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