Grain boundary oxidation of proton-irradiated nuclear grade stainless steel in simulated primary water of pressurized water reactor (vol 11, 1371, 2021)

doi:10.1038/s41598-021-88868-3

CORC > 金属研究所 > 中国科学院金属研究所

	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
刊名	SCIENTIFIC REPORTS
	2021-04-22
卷号	11 期号:1 页码:1
ISSN号	2045-2322
DOI	10.1038/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
出版者	NATURE RESEARCH
WOS记录号	WOS:000642742500128
内容类型	期刊论文
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.