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浏览/检索结果: 共6条，第1-6条 帮助 限定条件 学科主题：Materials Science, Multidisciplinary     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 Ab initio molecular dynamics simulation on interfacial reaction behavior of Fe-Cr-Ni stainless steel in high temperature water 期刊论文 COMPUTATIONAL MATERIALS SCIENCE, 2018, 卷号: 149, 页码: 143-152 作者:  Wang, HT;  Han, EH;  Wang, HT (reprint author), Chinese Acad Sci, Inst Met Res, CAS Key Lab Nucl Mat & Safety Assessment, Shenyang 110016, Liaoning, Peoples R China. 收藏  |  浏览/下载：23/0  |  提交时间：2018/06/05 Stress-corrosion Cracking  Generalized-gradient Approximation  Pwr Primary Water  Crevice Corrosion  Oxide-films  Dissociative Adsorption  Electrochemical Noise  Pressurized-water  Aqueous-solutions  Pure Water   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   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   Structural, mechanical and corrosion studies of Cr-rich inclusions in 152 cladding of dissimilar metal weld joint 期刊论文 JOURNAL OF NUCLEAR MATERIALS, 2018, 卷号: 498, 页码: 9-19 作者:  Li, YF;  Wang, JQ;  Han, EH;  Yang, CD;  Wang, JQ (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：35/0  |  提交时间：2018/06/05 Pressurized-water Reactors  Environmentally-assisted Cracking  Safe-end  Quantitative Assessment  Secondary-side  Residual-stresses  High-temperature  Fusion Boundary  Base Alloys  Part 1   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