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

doi:10.1007/s40195-020-01123-y

IMR OpenIR

	Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water
	Deng, Ping 1,2; Han, En-Hou 1; Peng, Qunjia 1,3; Sun, Chen 4
通讯作者	Han, En-Hou(ehhan@imr.ac.cn)
	2020-08-18
发表期刊	ACTA METALLURGICA SINICA-ENGLISH LETTERS
ISSN	1006-7191
页码	13
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.
关键词	Stainless steel Irradiation High-temperature corrosion Intergranular corrosion
资助者	International Science & Technology Cooperation Program of China ; Essential Research Fund by SNPTC
DOI	10.1007/s40195-020-01123-y
收录类别	SCI
语种	英语
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
WOS类目	Metallurgy & Metallurgical Engineering
WOS记录号	WOS:000560642400001
出版者	CHINESE ACAD SCIENCES, INST METAL RESEARCH
引用统计	被引频次：3[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/140358
专题	中国科学院金属研究所
通讯作者	Han, En-Hou
作者单位	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
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.