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浏览/检索结果: 共7条，第1-7条 帮助 已选(0)清除 条数/页：5101520253035404550556065707580859095100   排序方式：请选择作者升序作者降序题名升序题名降序发表日期升序发表日期降序提交时间升序提交时间降序 Corrosion resistance of 316 stainless steel in a simulated pressurized water reactor improved by laser cladding with chromium 期刊论文 Surface and Coatings Technology, 2022, 卷号: 441 作者:  Gu, Yufen 收藏  |  浏览/下载：42/0  |  提交时间：2022/06/20 Austenitic stainless steel  Chromium compounds  Corrosion resistance  Corrosion resistant coatings  Laser cladding  Light water reactors  Morphology  Nuclear fuels  Oxide films  Pressurized water reactors  Steel corrosion  316 austenitic stainless steel  316 stainless steel  Cr coatings  Electrochemical behaviors  Element distribution  Oxidation behaviours  Powder bed  Powder bed fusion  Pressurised water reactor  Stress-corrosion   Microstructure and stress corrosion cracking of a SA508-309L/308L-316L dissimilar metal weld joint in primary pressurized water reactor environment 期刊论文 JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2020, 卷号: 40, 页码: 1-14 作者:  Dong, Lijin;  Ma, Cheng;  Peng, Qunjia;  Han, En-Hou;  Ke, Wei 收藏  |  浏览/下载：89/0  |  提交时间：2021/02/02 Dissimilar metal weld joint  Stress corrosion cracking  Microstructure  Primary pressurized water reactor environment  Slow strain rate tension   Microstructure and stress corrosion cracking of a SA508-309L/308L-316L dissimilar metal weld joint in primary pressurized water reactor environment 期刊论文 JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2020, 卷号: 40, 页码: 1-14 作者:  Dong, Lijin;  Ma, Cheng;  Peng, Qunjia;  Han, En-Hou;  Ke, Wei 收藏  |  浏览/下载：89/0  |  提交时间：2021/02/02 Dissimilar metal weld joint  Stress corrosion cracking  Microstructure  Primary pressurized water reactor environment  Slow strain rate tension   Correlation of microstructure and stress corrosion cracking initiation behaviour of the fusion boundary region in a SA508 Cl. 3-Alloy 52M dissimilar weld joint in primary pressurized water reactor environment 期刊论文 CORROSION SCIENCE, 2018, 卷号: 132, 页码: 9-20 作者:  Dong, LJ;  Peng, QJ;  Xue, H;  Han, EH;  Ke, W 收藏  |  浏览/下载：66/0  |  提交时间：2018/06/05 Low-alloy Steel  High-temperature Water  Heat-affected Zone  Bwr Coolant Environments  Grain-boundary  Metal Weld  Assisted Cracking  Stainless-steel  Chromium Depletion  Residual-stress   Effect of dissolved oxygen content on stress corrosion cracking of a cold worked 316L stainless steel in simulated pressurized water reactor primary water environment 期刊论文 Journal of Nuclear Materials, 2014, 卷号: 446, 期号: 1-3, 页码: 15-26 L. T. Zhang; J. Q. Wang 收藏  |  浏览/下载：21/0  |  提交时间：2014/04/18 high-temperature water  assisted cracking  alloy 690tt  pure water  growth  behavior  dependence  chemistry  coolant  model   The electrochemical behavior of A508III low alloy steel in simulated pressurized water reactor primary water solutions 会议论文 2014 Electrochemical Conference on Energy and the Environment, ECEE 2014, 2014-03-13 作者:  Xiao, Qian[1];  Lu, Zhanpeng[2];  Chen, Junjie[3];  Xia, Xiaofeng[4] 收藏  |  浏览/下载：2/0  |  提交时间：2019/04/30 Dynamic simulations of primary frequency regulation for pressurized water reactor nuclear power generation units 期刊论文 Dianwang Jishu/Power System Technology, 2013, 卷号: 37, 期号: [db:dc_citation_issue], 页码: 3197-3201 作者:  Tang, Zhenpeng;  Chen, Shihe;  Wu, Yuzhong;  Wang, Pengfei;  Fang, Huawei 收藏  |  浏览/下载：5/0  |  提交时间：2019/12/03 Dynamic link library files  MATLAB/Simulink environment  Matlab/Simulink simulation  Power grid frequencies  Primary frequency regulation  Primary frequency regulations (PFR)  S function  Time-varying dynamics