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

doi:10.1007/s40195-020-01123-y

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	Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water
	Deng, Ping 2,4; Han, En-Hou 2; Peng, Qunjia 1,2; Sun, Chen 3
刊名	ACTA METALLURGICA SINICA-ENGLISH LETTERS
	2020-08-18
页码	13
关键词	Stainless steel Irradiation High-temperature corrosion Intergranular corrosion
ISSN号	1006-7191
DOI	10.1007/s40195-020-01123-y
通讯作者	Han, En-Hou(ehhan@imr.ac.cn)
英文摘要	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.
资助项目	International Science & Technology Cooperation Program of China[2014DFA50800] ; Essential Research Fund by SNPTC[2015SN010-007]
WOS研究方向	Metallurgy & Metallurgical Engineering
语种	英语
出版者	CHINESE ACAD SCIENCES, INST METAL RESEARCH
WOS记录号	WOS:000560642400001
资助机构	International Science & Technology Cooperation Program of China ; Essential Research Fund by SNPTC
内容类型	期刊论文
源URL	[http://ir.imr.ac.cn/handle/321006/140357]
专题	金属研究所_中国科学院金属研究所
通讯作者	Han, En-Hou
作者单位	1.Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China 2.Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China 3.State Power Investment Corp Res Inst, Beijing 102209, Peoples R China 4.Nucl Power Inst China, Chengdu 610213, Peoples R China
推荐引用方式 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,2020:13.
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,13.
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):13.