机构

• 金属研究所 [6]
• 上海应用物理研究所 [1]

采集方式

• OAI收割 [7]

内容类型

• 期刊论文 [7]

发表日期

• 2020 [2]
• 2019 [1]
• 2018 [1]
• 2015 [2]
• 2014 [1]

学科主题

• Materials ... [1]
• Metallurgy... [1]

筛选

浏览/检索结果: 共7条，第1-7条 帮助 条数/页： 5101520253035404550556065707580859095100 排序方式： 请选择题名升序题名降序提交时间升序提交时间降序作者升序作者降序发表日期升序发表日期降序 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  OAI收割 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：130/0  |  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  OAI收割 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：76/0  |  提交时间：2021/02/02 Dissimilar metal weld joint  Stress corrosion cracking  Microstructure  Primary pressurized water reactor environment  Slow strain rate tension   Assessment of Thermal Aging of Austenitic Stainless Steel Weld Metal by Using the Double Loop Electrochemical Potentiokinetic Reactivation Technique 期刊论文  OAI收割 CORROSION, 2019, 卷号: 75, 期号: 4, 页码: 377-388 作者:  Lin, Xiaodong;  Peng, Qunjia;  Han, En-Hou;  Ke, Wei   |  收藏  |  浏览/下载：117/0  |  提交时间：2021/02/02 electrochemical potentiokinetic reactivation  nanoindentation hardness  pressurized water reactor  reactivation ratio  stainless steel weld metal  thermal aging   Evaluation of stress corrosion cracking susceptibility of forged 316 stainless steel in simulated primary water 期刊论文  OAI收割 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：27/0  |  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   Influence of later-dissolved oxygen on microstructural changes in oxide films formed on Alloy 690TT in hydrogenated primary water 期刊论文  OAI收割 Corrosion Science, 2015, 卷号: 94, 页码: 245-254 Z. M.; Wang Zhang, J. Q.; Han, E. H.; Ke, W. 收藏  |  浏览/下载：15/0  |  提交时间：2015/05/08 Nickel  SEM  TEM  High temperature corrosion  Oxidation  high-temperature water  stress-corrosion cracking  ni-base alloys  reactor primary conditions  type-316 stainless-steel  different  surface-states  simulated primary water  x-ray photoelectron  nickel-based alloys  pressurized-water   Supercritical water oxidation of spent extraction solvent simulants 期刊论文  OAI收割 NUCLEAR SCIENCE AND TECHNIQUES, 2015, 卷号: 26, 期号: 3, 页码: — 作者:  Wang, S;  Qin, Q;  Chen, K;  Xia, XB;  Ma, HJ 收藏  |  浏览/下载：27/0  |  提交时间：2016/03/04 CRITICAL PRESSURIZED-WATER  WASTE-WATER  CHEMICAL-REACTIONS  AQUEOUS-SOLUTIONS  HIGH-TEMPERATURE  FERRITIC STEELS  CORROSION  KINETICS  REACTOR  OXYGEN   Comparison of Corrosion Resistance of UNS N06690TT and UNS N08800SN in Simulated Primary Water with Various Concentrations of Dissolved Oxygen 期刊论文  OAI收割 Corrosion, 2014, 卷号: 70, 期号: 6, 页码: 598-614 J. Q. Wang; X. H. Li; F. Huang; Z. M. Zhang; J. Z. Wang; R. W. Staehle 收藏  |  浏览/下载：43/0  |  提交时间：2014/07/03 dissolved oxygen  electrochemical impedance spectroscopy  pressurized  water reactor primary water  UNS N06690  UNS N08800  high-temperature  alloy 690  dissolution  behavior  cracking  reactor  films