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Distribution and Characteristics of Oxide Films Formed on Stainless Steel Cladding on Low Alloy Steel in Simulated PWR Primary Water Environments 会议论文
PROCEEDINGS OF THE 18TH INTERNATIONAL CONFERENCE ON ENVIRONMENTAL DEGRADATION OF MATERIALS IN NUCLEAR POWER SYSTEMS - WATER REACTORS, VOL 2, 2018-01-01
作者:  Xiong, Qi[1];  Li, Hongjuan[2];  Lu, Zhanpeng[3];  Chen, Junjie[4];  Xiao, Qian[5]
收藏  |  浏览/下载:11/0  |  提交时间:2019/04/22
The oxidation behavior of 316L in simulated pressurized water reactor environments with cyclically changing concentrations of dissolved oxygen and hydrogen 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 511, 页码: 417-427
作者:  Zhong, Xiangyu[1];  Xia, Shuang[2];  Xu, Jian[3];  Shoji, Tetsuo[4]
收藏  |  浏览/下载:10/0  |  提交时间:2019/04/22
Characterization of microstructure, local deformation and microchemistry in Alloy 690 heat-affected zone and stress corrosion cracking in high temperature water 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2015, 卷号: 465, 页码: 471-481
作者:  Lu, Zhanpeng[1];  Chen, Junjie[2];  Shoji, Tetsuo[3];  Takeda, Yoichi[4];  Yamazaki, Seiya[5]
收藏  |  浏览/下载:2/0  |  提交时间:2019/04/26
Improving the oxidation resistance of 316L stainless steel in simulated pressurized water reactor primary water by electropolishing treatment 期刊论文
JOURNAL OF NUCLEAR MATERIALS, 2015, 卷号: 467, 页码: 194-204
作者:  Han, Guangdong[1];  Lu, Zhanpeng[2];  Ru, Xiangkun[3];  Chen, Junjie[4];  Xiao, Qian[5]
收藏  |  浏览/下载:3/0  |  提交时间:2019/04/30


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