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

IMR OpenIR

	Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor
	Deng, Ping 1,2; Peng, Qunjia 1,3; Han, En-Hou 2
通讯作者	Peng, Qunjia(pengqunjia@yahoo.com)
	2021-01-14
发表期刊	SCIENTIFIC REPORTS
ISSN	2045-2322
卷号	11 期号:1 页码:9
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.
资助者	International Science & Technology Cooperation Program of China
DOI	10.1038/s41598-020-80600-x
收录类别	SCI
语种	英语
资助项目	International Science & Technology Cooperation Program of China[2014DFA50800]
WOS研究方向	Science & Technology - Other Topics
WOS类目	Multidisciplinary Sciences
WOS记录号	WOS:000626774100085
出版者	NATURE RESEARCH
引用统计	被引频次：9[WOS] [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	http://ir.imr.ac.cn/handle/321006/161070
专题	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.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
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.