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Pressure vessel Technology
FQ: 月刊
AD of Publication: 安徽省合肥市
Lanuage: 中文;
ISSN: 1001-4837
CN: 34-1058/TH
YP: 1984
Url: 中国机械工程学会压力容器分会
Recommended Journals
Pressure vessel Technology
2018 -02
Welding Repair Technology of Large Cr-Mo Steel Coke Drums ZHANG Shao-liang;REN Ming-hao;BO Hua-quan;CNOOC Huizhou Petrochemicals Co.
Thermo-mechanical Coupling Analysis of Pipeline in Crossing Construction of Large Excavation WANG Guo-mao;ZHAO Xiao;WEI Li-hong;PetroChina Southwest Pipeline Company
Corrosion Leakage Analysis of Slurry Evaporator MA Hong-jie;GONG Shu-peng;WANG Xiang-ru;Research Institute of Petrochina Dushanzi Petrochemical Company;Science and Technology Bureau of Petrochina Dushanzi Petrochemical Company;
Experimental and Numerical Studies on Fatigue Crack Propagation of Surface Cracks in Heat-Resistant Steel CrMoCoV Considering Closure Effect XIA Qi-wei;GONG Jian-guo;XUAN Fu-zhen;Key Laboratory of Pressure Systems and Safety
Dilution Research for C Element of Austenite Stainless Cladding Welds LIAO Guo-ping;LIU Zi-jun;ZHANG Tao;LIU Hong-jie;Dongfang Electric Corporation
Failure Analysis on Heat Exchanger Tubes of Tower Overhead Condenser YI Cheng;ZHOU Chao;Wuhuan Engineering Co.
Leak Failure Analysis on CO_2 High Pressure Cylinder under Hydrostatic Test in Periodic Inspection XU Shu-fang;HUANG Guo-gen;LIU Zhao-hua;YIN Xie-ping;Zhejiang Gross Seamless Steel Tube Co.
Exploitation of 16MND5 Steel Plates for Nuclear Reactor Pressure Vessel WANG Shuang;YAN Bing-yu;HU Hai-yang;SUN Dian-dong;State Key Laboratory of Metal Material for Marine Equipment and Application;Angang Steel Company Limited;
Sealing Performance Analysis of Blasting Valve Based on Fine Bolt Model by Thermomechanical Coupling ZHANG Ji;ZHAO Guo-zhong;ZHANG Hao;ZHANG Li;State Key Laboratory of Structural Analysis for Industrial Equipment
Fatigue Analysis for Screw Threads of Reactor Pressure Vessel Stud CHEN Tao;LIU Pan;XU Xiao;China Nuclear Power Design Company
Design Optimization for Fixed Point of Pump Sealing Pipes in the Project WU Qi;LIU Xue-lin;Wuhan Haiwang New Energy Engineering & Technology Co.
Introduction to Fatigue Analysis Methods of Nuclear Grade 2 & 3 Pipelines LIU Xue-lin;LIU Mei-ping;China Nuclear Power Design Co.
2018 Issues:  [02] [01]
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