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浏览/检索结果: 共17条，第1-10条 帮助 限定条件 学科主题：Metallurgy & Metallurgical Engineering     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 Comparative study of microstructure and properties of low-alloy-steel/nickel-based-alloy interfaces in dissimilar metal weld joints prepared by different GTAW methods 期刊论文 MATERIALS CHARACTERIZATION, 2018, 卷号: 139, 页码: 186-196 作者:  Ming, HL;  Wang, JQ;  Han, EH;  Wang, JQ (reprint author), Chinese Acad Sci, Inst Met Res, Liaoning Key Lab Safety & Assessment Tech Nucl Ma, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Peoples R China. 收藏  |  浏览/下载：21/0  |  提交时间：2018/06/05 Local Mechanical-properties  Dip Cracking Susceptibility  Stress-corrosion Cracking  Fusion Boundary Region  Safe-end  Ferritic Steel  Part 1   Effect of pH on corrosion behavior of 316L stainless steel in hydrogenated high temperature water 期刊论文 MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2018, 卷号: 69, 期号: 5, 页码: 580-589 作者:  Wang, JZ;  Wang, JQ;  Ming, HL;  Zhang, ZM;  Han, EH 收藏  |  浏览/下载：19/0  |  提交时间：2018/06/05 Simulated Primary Water  Dissolved-oxygen Concentration  Crack-growth Kinetics  Surface Oxide-films  Pwr Primary Water  Alloy 690  Pressurized-water  Electrochemical-behavior  Aqueous Environments  Nickel-alloys   Irradiation-induced segregation at phase boundaries in austenitic stainless steel weld metal 期刊论文 SCRIPTA MATERIALIA, 2018, 卷号: 149, 页码: 11-15 作者:  Lin, XD;  Peng, QJ;  Han, EH;  Ke, W;  Sun, C 收藏  |  浏览/下载：31/0  |  提交时间：2018/06/05 Radiation-induced Segregation  Stress-corrosion Cracking  Atom-probe Tomography  Intergranular Corrosion  Specimen Preparation  Neutron-irradiation  Primary Water  Aisi 316l  Stability  Evolution   Fretting corrosion fatigue of Alloy 690 in high-temperature pure water 期刊论文 CORROSION SCIENCE, 2018, 卷号: 133, 页码: 423-431 作者:  Liao, JP;  Wu, XQ;  Tan, JB;  Tang, LC;  Qian, H 收藏  |  浏览/下载：26/0  |  提交时间：2018/06/05 Steam-generator Tubes  Surface Oxide-films  Crevice Corrosion  Stress-corrosion  Stainless-steel  Wear Behavior  Nickel-alloys  304-stainless-steel  Environments  Mechanism   Characteristics of Oxidation and Oxygen Penetration of Alloy 690 in 600 degrees C Aerated Supercritical Water 期刊论文 JOURNAL OF MATERIALS SCIENCE & TECHNOLOGY, 2018, 卷号: 34, 期号: 3, 页码: 561-569 作者:  Zhong, XY;  Wu, XQ;  Han, EH;  Zhong, XY (reprint author), Chinese Acad Sci, Inst Met Res, Liaoning Key Lab Safety & Assessment Tech Nucl Ma, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China. 收藏  |  浏览/下载：33/0  |  提交时间：2018/06/05 High-temperature Water  Nickel-base Alloys  Stress-corrosion Cracking  Surface Oxide-films  Intergranular Oxidation  Elevated-temperatures  Electron-microscopy  Internal Oxidation  Chromium Alloys  Behavior   Evaluation of stress corrosion cracking susceptibility of forged 316 stainless steel in simulated primary water 期刊论文 MATERIALS AND CORROSION-WERKSTOFFE UND KORROSION, 2018, 卷号: 69, 期号: 3, 页码: 328-336 作者:  Zhu, RL;  Wang, JQ;  Ming, HL;  Zhang, ZM;  Han, EH 收藏  |  浏览/下载：22/0  |  提交时间：2018/06/05 High-temperature Water  Environmentally Assisted Cracking  Reactor Primary Water  Pwr Primary Water  Pressurized-water  Dissolved-oxygen  Oxidation Behavior  Nickel-alloys  Growth  Metal   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   An attempt to correlate the change of the swept area (Delta A/b(2)) by mobile dislocations with the mechanism of the fatigue crack propagation rate (da/dN) in environmental hydrogen: Application in Inconel 690 期刊论文 MATERIALS SCIENCE AND ENGINEERING A-STRUCTURAL MATERIALS PROPERTIES MICROSTRUCTURE AND PROCESSING, 2018, 卷号: 709, 页码: 349-357 作者:  Luo, XH;  Habashi, M;  Luo, XH (reprint author), Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang, Liaoning, Peoples R China. 收藏  |  浏览/下载：8/0  |  提交时间：2018/06/05 Stress-corrosion Cracking  Austenitic Stainless-steel  Alloy-600  Nickel  Water   Effect of the Amount of Cold Work on Corrosion of Type 304 Nuclear Grade Stainless Steel in High-Temperature Water 期刊论文 NATL ASSOC CORROSION ENG, 2017, 卷号: 73, 期号: 10, 页码: 1237-1249 作者:  Deng, Ping;  Peng, Qunjia;  Han, En-Hou;  Ke, Wei;  Peng, QJ (reprint author), Chinese Acad Sci, Inst Met Res, Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China. 收藏  |  浏览/下载：19/0  |  提交时间：2018/01/10 Autoclave Testing  Cold Work  Corrosion Rate  Stainless Steels  Transmission Electron Microscope   Effect of irradiation on corrosion of 304 nuclear grade stainless steel in simulated PWR primary water 期刊论文 PERGAMON-ELSEVIER SCIENCE LTD, 2017, 卷号: 127, 页码: 91-100 作者:  Deng, Ping;  Peng, Qunjia;  Han, En-Hou;  Ke, Wei;  Sun, Chen 收藏  |  浏览/下载：20/0  |  提交时间：2018/01/10 Stainless Steel  Tem  High Temperature Corrosion  Intergranular Corrosion