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Corrosion Behavior and Mechanism of Irradiated 304 Nuclear Grade Stainless Steel in High-Temperature Water
Deng, Ping1,2; Han, En-Hou1; Peng, Qunjia1,3; Sun, Chen4
Corresponding AuthorHan, En-Hou(ehhan@imr.ac.cn)
2020-08-18
Source PublicationACTA METALLURGICA SINICA-ENGLISH LETTERS
ISSN1006-7191
Pages13
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.
KeywordStainless steel Irradiation High-temperature corrosion Intergranular corrosion
Funding OrganizationInternational Science & Technology Cooperation Program of China ; Essential Research Fund by SNPTC
DOI10.1007/s40195-020-01123-y
Indexed BySCI
Language英语
Funding ProjectInternational Science & Technology Cooperation Program of China[2014DFA50800] ; Essential Research Fund by SNPTC[2015SN010-007]
WOS Research AreaMetallurgy & Metallurgical Engineering
WOS SubjectMetallurgy & Metallurgical Engineering
WOS IDWOS:000560642400001
PublisherCHINESE ACAD SCIENCES, INST METAL RESEARCH
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Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/140358
Collection中国科学院金属研究所
Corresponding AuthorHan, En-Hou
Affiliation1.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
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,2020:13.
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.
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