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Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water
Deng, Ping; Han, En-Hou; Peng, Qunjia; Sun, Chen
2020-09-02
Source PublicationACTA METALLURGICA SINICA-ENGLISH LETTERS
AbstractCorrosion 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.
DOI10.1007/s40195-020-01123-y
WOS IDWOS:000560642400001
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Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/82613
Collection中国科学院金属研究所
Recommended Citation
GB/T 7714
Deng, Ping,Han, En-Hou,Peng, Qunjia,et al. Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water[J]. ACTA METALLURGICA SINICA-ENGLISH LETTERS,2020.
APA Deng, Ping,Han, En-Hou,Peng, Qunjia,&Sun, Chen.(2020).Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water.ACTA METALLURGICA SINICA-ENGLISH LETTERS.
MLA Deng, Ping,et al."Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water".ACTA METALLURGICA SINICA-ENGLISH LETTERS (2020).
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