Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor

doi:10.1038/s41598-020-80600-x

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	Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
	Deng, Ping 2,3; Peng, Qunjia 1,2; Han, En-Hou 3
刊名	SCIENTIFIC REPORTS
	2021-01-14
卷号	11 期号:1 页码:9
ISSN号	2045-2322
DOI	10.1038/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
出版者	NATURE RESEARCH
WOS记录号	WOS:000626774100085
资助机构	International Science & Technology Cooperation Program of China
内容类型	期刊论文
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.Suzhou Nucl Power Res Inst, Suzhou 215004, Peoples R China 2.Nucl Power Inst China, Chengdu 610213, 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.