中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor (vol 11, 1371, 2021)

文献类型:期刊论文

作者Deng, Ping; Peng, Qunjia; Han, En-Hou
刊名SCIENTIFIC REPORTS
出版日期2021-04-22
卷号11期号:1页码:1
ISSN号2045-2322
DOI10.1038/s41598-021-88868-3
英文摘要An amendment to this paper has been published and can be accessed via a link at the top of the paper.
WOS研究方向Science & Technology - Other Topics
语种英语
WOS记录号WOS:000642742500128
出版者NATURE RESEARCH
源URL[http://ir.imr.ac.cn/handle/321006/161343]  
专题金属研究所_中国科学院金属研究所
作者单位Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
推荐引用方式
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.

入库方式: OAI收割

来源:金属研究所

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