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Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor (vol 11, 1371, 2021)
Deng, Ping; Peng, Qunjia; Han, En-Hou
2021-04-22
Source PublicationSCIENTIFIC REPORTS
ISSN2045-2322
Volume11Issue:1Pages:1
AbstractAn amendment to this paper has been published and can be accessed via a link at the top of the paper.
DOI10.1038/s41598-021-88868-3
Indexed BySCI
Languageen
WOS Research AreaScience & Technology - Other Topics
WOS SubjectMultidisciplinary Sciences
WOS IDWOS:000642742500128
PublisherNATURE RESEARCH
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Document Type期刊论文
Identifierhttp://ir.imr.ac.cn/handle/321006/161344
Collection中国科学院金属研究所
AffiliationChinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, 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 (vol 11, 1371, 2021)[J]. SCIENTIFIC REPORTS,2021,11(1):1.
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 (vol 11, 1371, 2021).SCIENTIFIC REPORTS,11(1),1.
MLA Deng, Ping,et al."Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor (vol 11, 1371, 2021)".SCIENTIFIC REPORTS 11.1(2021):1.
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