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Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
Deng, Ping1,2; Peng, Qunjia1,3; Han, En-Hou2
Corresponding AuthorPeng, Qunjia(pengqunjia@yahoo.com)
2021-01-14
Source PublicationSCIENTIFIC REPORTS
ISSN2045-2322
Volume11Issue:1Pages:9
AbstractGrain boundary (GB) oxidation of proton-irradiated 304 nuclear grade stainless steel in primary water of pressurized water reactor was investigated. The investigation was conducted by studying microstructure of the oxide and oxide precursor formed at GB on an "atom-by-atom" basis by a combination of atom-probe tomography and transmission electron microscope. The results revealed that increasing irradiation dose promoted the GB oxidation, in correspondence with a different oxide and oxide precursor formed at the GB. Correlation of the oxide and oxide precursor with the GB oxidation behavior has been discussed in detail.
Funding OrganizationInternational Science & Technology Cooperation Program of China
DOI10.1038/s41598-020-80600-x
Indexed BySCI
Languageen
Funding ProjectInternational Science & Technology Cooperation Program of China[2014DFA50800]
WOS Research AreaScience & Technology - Other Topics
WOS SubjectMultidisciplinary Sciences
WOS IDWOS:000626774100085
PublisherNATURE RESEARCH
Citation statistics
Cited Times:3[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/161070
Collection中国科学院金属研究所
Corresponding AuthorPeng, Qunjia
Affiliation1.Nucl Power Inst China, Chengdu 610213, Peoples R China
2.Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
3.Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China
Recommended Citation
GB/T 7714
Deng, Ping,Peng, Qunjia,Han, En-Hou. Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor[J]. SCIENTIFIC REPORTS,2021,11(1):9.
APA Deng, Ping,Peng, Qunjia,&Han, En-Hou.(2021).Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor.SCIENTIFIC REPORTS,11(1),9.
MLA Deng, Ping,et al."Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor".SCIENTIFIC REPORTS 11.1(2021):9.
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