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

被引：3
作者：
Deng, Ping [1 ,2 ]
Han, En-Hou [1 ]
Peng, Qunjia [1 ,3 ]
Sun, Chen [4 ]
机构：
[1] Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
[2] Nucl Power Inst China, Chengdu 610213, Peoples R China
[3] Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China
[4] State Power Investment Corp Res Inst, Beijing 102209, Peoples R China
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：
Stainless steel; Irradiation; High-temperature corrosion; Intergranular corrosion; LOCALIZED DEFORMATION; OXIDATION BEHAVIOR; AQUEOUS CORROSION; IASCC INITIATION; CRACKING;
D O I：
10.1007/s40195-020-01123-y
中图分类号：
TF [冶金工业];
学科分类号：
0806 ;
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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