中文版 | English

在结果中检索

IMR OpenIR

浏览/检索结果: 共14条，第1-10条 帮助

已选(0)清除 条数/页：   排序方式：
Influence of chromium of low content on the corrosion behavior of SA106B carbon steels in high-temperature pressurized LiOH medium 期刊论文
NUCLEAR ENGINEERING AND DESIGN, 2023, 卷号: 414, 页码: 10
作者:  Zheng, Kexin;  Hu, Hongxiang;  Wang, Zhengbin;  Zheng, Yugui;  Shang, Xianhe;  Zhang, Wei;  Zhao, Liang
收藏  |  浏览/下载：2/0  |  提交时间：2025/04/27
Electrochemical measurements  Nuclear power plant  Carbon Steel  Lithium hydroxide corrosion  High-temperature corrosion  Oxidation  
Fracture Analysis and Working Stress Calculation of Bearing Cage Used in Charging Pump in a Nuclear Power Plant 期刊论文
METALS, 2023, 卷号: 13, 期号: 8, 页码: 14
作者:  Chen, Qiang;  Jiang, Shengli;  Duan, Deli
收藏  |  浏览/下载：7/0  |  提交时间：2024/01/08
bearing  cage  fatigue fracture  finite element calculation  nuclear power plant  
Reaction Mechanism of High-Temperature Corium Pool of Core 期刊论文
RARE METAL MATERIALS AND ENGINEERING, 2022, 卷号: 51, 期号: 3, 页码: 913-920
作者:  Xue Baoquan;  Yang Yaqian;  Liang Tian;  Chen Bo;  Ma Yingche;  Liu Kui;  Shan Hongyi;  Kang Taifeng;  Gu Peiwen
收藏  |  浏览/下载：128/0  |  提交时间：2022/07/01
nuclear power safety  severe accident  in-vessel corium retention  molten zirconia  stratification mechanism  
Numerical Investigation on Residual Stresses of the Safe-End/Nozzle Dissimilar Metal Welded Joint in CAP1400 Nuclear Power Plants 期刊论文
ACTA METALLURGICA SINICA-ENGLISH LETTERS, 2019, 卷号: 32, 期号: 5, 页码: 618-628
作者:  Dong, Wen-Chao;  Gao, Dian-Bao;  Lu, Shan-Ping
收藏  |  浏览/下载：115/0  |  提交时间：2021/02/02
CAP1400 nuclear power plants  Nozzle  Safe-end  Dissimilar metal welding  Residual stress  
Microstructure of a domestically fabricated dissimilar metal weld joint (SA508-52M-309L-CF8A) in nuclear power plant 期刊论文
MATERIALS CHARACTERIZATION, 2019, 卷号: 148, 页码: 100-115
作者:  Ming, Hongliang;  Zhang, Zhiming;  Wang, Jianqiu;  Han, En-Hou
收藏  |  浏览/下载：144/0  |  提交时间：2021/02/02
Dissimilar metal weld joint  GTAW  Microstructure  Duplex stainless steel  Nuclear power plant  
Design of single-phase high-entropy alloys composed of low thermal neutron absorption cross-section elements for nuclear power plant application 期刊论文
INTERMETALLICS, 2019, 卷号: 104, 页码: 143-153
作者:  Xiang, C.;  Han, E-H;  Zhang, Z. M.;  Fu, H. M.;  Wang, J. Q.;  Zhang, H. F.;  Hu, G. D.
收藏  |  浏览/下载：161/0  |  提交时间：2021/02/02
High-entropy alloys  Alloy design  Mechanical properties  Nuclear power plant  Accident tolerant fuel  
Evaluation of Fatigue Properties of CA6NM Martensite Stainless Steel Using Miniature Specimens 期刊论文
ACTA METALLURGICA SINICA, 2018, 卷号: 54, 期号: 10, 页码: 1359-1367
作者:  Ma Yefei;  Song Zhuman;  Zhang Siqian;  Chen Lijia;  Zhang Guangping
收藏  |  浏览/下载：125/0  |  提交时间：2021/02/02
martensite stainless steel  fatigue property  miniature specimen  size effect  nuclear power material  
The repassivation kinetics study of Alloy 800 in high-temperature pressurized water 期刊论文
ELECTROCHEMISTRY COMMUNICATIONS, 2015, 卷号: 60, 页码: 100-103
作者:  Wang, Jiazhen;  Han, En-Hou;  Wang, Jianqiu;  ehhan@imr.ac.cn
收藏  |  浏览/下载：159/0  |  提交时间：2016/04/21
Repassivation  Alloy 800  High-temperature Water  Stress Corrosion Cracking  Nuclear Power  
Effect of carbon and niobium on the microstructure and impact toughness of a high silicon 12% Cr ferritic/martensitic heat resistant steel 期刊论文
Materials Science and Engineering a-Structural Materials Properties Microstructure and Processing, 2014, 卷号: 616, 页码: 12-19
作者:  Z. F. Ye;  P. Wang;  D. Z. Li;  Y. T. Zhang;  Y. Y. Li
收藏  |  浏览/下载：123/0  |  提交时间：2015/01/14
High Silicon 12% Cr Ferritic/martensitic Steel  Primary Nbc  Carbonitride  Thermodynamic Calculations  Impact Toughness  Ferritic Martensitic Steels  Si-enriched Steels  Mechanical-properties  Lead-bismuth  Power-plant  Corrosion-resistance  Nuclear-reactors  Creep  Strength  Temperature  Precipitation  
Fracture toughness and fracture behavior of SA508-III steel at different temperatures 期刊论文
INTERNATIONAL JOURNAL OF MINERALS METALLURGY AND MATERIALS, 2014, 卷号: 21, 期号: 12, 页码: 1187-1195
作者:  Liu Jiahua;  Wang Lei;  Liu Yang;  Song Xiu;  Luo Jiong;  Yuan Dan
收藏  |  浏览/下载：159/0  |  提交时间：2021/02/26
PRESSURE-VESSEL STEELS  CYCLE FATIGUE BEHAVIOR  CU-RICH CLUSTERS  MECHANICAL-PROPERTIES  CARBIDE DISTRIBUTION  STAINLESS-STEEL  SA-508 STEEL  CRACK-GROWTH  PRECIPITATION  ENVIRONMENTS  low alloyed steel  fracture toughness  fracture behavior  temperature  dynamic strain aging  nuclear power plants