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

文献类型:期刊论文

作者Deng, Ping1,3; Peng, Qunjia1,2; Han, En-Hou3
刊名SCIENTIFIC REPORTS
出版日期2021-01-14
卷号11期号:1页码:9
ISSN号2045-2322
DOI10.1038/s41598-020-80600-x
通讯作者Peng, Qunjia(pengqunjia@yahoo.com)
英文摘要Grain 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.
资助项目International Science & Technology Cooperation Program of China[2014DFA50800]
WOS研究方向Science & Technology - Other Topics
语种英语
WOS记录号WOS:000626774100085
出版者NATURE RESEARCH
资助机构International Science & Technology Cooperation Program of China
源URL[http://ir.imr.ac.cn/handle/321006/161069]  
专题金属研究所_中国科学院金属研究所
通讯作者Peng, Qunjia
作者单位1.Nucl Power Inst China, Chengdu 610213, Peoples R China
2.Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China
3.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[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.

入库方式: OAI收割

来源:金属研究所

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