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浏览/检索结果: 共4条，第1-4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 sigma-Phase Precipitation Mechanism of 15Cr-15Ni Titanium-Modified Austenitic Stainless Steel During Long-Term Thermal Exposure 期刊论文 ACTA METALLURGICA SINICA-ENGLISH LETTERS, 2018, 卷号: 31, 期号: 3, 页码: 281-289 作者:  Wang, ZN;  Liang, T;  Xing, WW;  Du, AB;  Gao, M 收藏  |  浏览/下载：30/0  |  提交时间：2018/06/05 Reactor Applications  Creep Strength  Temperature  Cr  Ti  Kinetics  Elements  Cracking  Fission  Mo   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   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