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

被引:0
|
作者
Deng, Ping [1 ]
Peng, Qunjia [1 ]
Han, En-Hou [1 ]
机构
[1] Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China
基金
对外科技合作项目(国际科技项目);
关键词
D O I
10.1038/s41598-021-88868-3
中图分类号
O [数理科学和化学]; P [天文学、地球科学]; Q [生物科学]; N [自然科学总论];
学科分类号
07 ; 0710 ; 09 ;
摘要
An amendment to this paper has been published and can be accessed via a link at the top of the paper.
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页数:1
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