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Nuclear Science and Engineering
FQ: quarterly
AD of Publication: China
Lanuage: English
ISSN: 0258-0918
CN: 11-1861/TL
YP: 1981
Recommended Journals
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2015 -01
Catalog
Study on Application of Grid and Physical Model in CFD Method ZHANG Ya-bo;ZHANG Dong-hui;China Zhongyuan Engineering Corporation;China Institute of Atomic Energe;
The Stress Intensity Factor Variation of Two Cracks Interaction in Nuclear Piping BAI Xin;XIE Li-yang;College of Mechanical Engineering & Automation
Automatic Modeling for the Monte Carlo transport code Geant4 NIE Fan-zhi;HU Li-qin;WANG Dong;WANG Guo-zhong;WANG Dian-xi;LONG Peng-cheng;WU Yi-can;University of Science and Technology of China;Institute of Nuclear Energy Safety Technology
Design and Heat Transfer Analysis of Rotating Tritium Target of10~(12)n/s D-T Fusion Neutron Generator WANG Gang;YU Qian-feng;WANG Wen;SONG Gang;WU Yi-can;Key Laboratory of Neutronics and Radiation Safety
Probability of Persistent Fission Chain Initiated by Neutrons in Moving Multiplying Assembly WANG Zhe;HONG Zhen-ying;Institute of Applied Physics and Computational Mathematics;
The Construction Technique Innovation for the Double-wall Containment of NPP and the Problems Needed for Discussion WANG Kai-hua;WEI Jian-guo;QIN Ya-lin;QIAN Fu-hua;SUN Chun-feng;ZHOU Shu-kui;YANG Jin-hui;Nanhua University;China Nuclear Engineering and Construction Corporation;
Sensitivity Analysis on Time of Reactor Coolant System Depressurization under Severe Accident for Generation Ⅱ+ Nuclear Power Plants CHONG Yi-min;YANG Zhi-yi;SHI Xue-yao;ZHANG Jia-jia;LI Chun;NI Man;XU Yu-ting;Nuclear and Radiation Safety Center
Study on the REA in Qinshan Ⅱ by Using PARCS/TRACE/ROBIN Codes FENG Jin-jun;HU Wei;ZHOU Ke-feng;LI Ming;XIAO Hong;CHAI Guo-han;Nuclear Safety and Radiation Center
Evaluation of SADV Capacity in PWR Nuclear Power Plant SHAO Ge;TONG Li-li;CAO Xue-wu;School of Mechanical Engineering
Study on Stability and Veracity of Pt/Air Sensor in Liquid Lead-bismuth ZHANG Min;WANG Yan-qing;WU Bin;WU Xin;GAO Sheng;HUANG Qun-ying;University of Science and Technology of China;Key Laboratory of Neutronics and Radiation Safety
Analysis and Improvement for the Residual Stress of the In-vessel ELM Coil in ITER LI Xiang-bin;JIN Huan;Institute of Plasma Physics
Assessment of Nucleate Boiling Correlations Applied to Thermal-hydraulic Code of Reactor LI Mei-lin;LIN Meng;YANG Yan-hua;ZHANG Hao;GONG Zhan;Shanghai Jiaotong University;Nuclear Power Software Development Center;
Analysis and Study on Core Power Capability with Margin Method LIU Tong-xian;WU Lei;YU Ying-rui;ZHOU Jin-man;Laboratory of Science and Technology on Reactor Design Technology
Preliminary Study on Internal Flooding Hazard Analysis Method for 1000MWe PWR NPP GUO Ding-qing;China Nuclear Power Design Co.
Investigation on Interim Storage of Spent Fuel for PWR NPP LIU Yan-zhang;WANG Xin;YUAN Cheng-yu;MO Huai-sen;China Nuclear Power Engineering Co.
The Control Rod Worth Measurement With Improved Neutron Source Multiplication Method SHI Yong-qian;LI Yi-guo;LU Jin;HONG Jing-yan;WU Xiao-bo;PENG Dan;China Institute of Atomic Energy;
Study on Bidirectional Shuffling Strategy of Breed-and-Burn Reactor CHEN Qi-chang;ZHAO Jin-kun;SI Sheng-yi;Shanghai Nuclear Engineering Research & Design Institute;
Study on Once-through Steam Generator Regional Proportional-Integral-Differential Feedwater Control System GUO Yan;LIU Zhi-hong;CHEN Bao-tong;LIU Xian-xing;LIU Cui-ying;Wuhan Second Ship Design and Research Institute;
Analysis of Interference on Over-temperature Protection Value ΔT in Nuclear Power Plant CHEN Yong-Wei;FU Jing-Qiang;China Nuclear Power Operations Co.
Fire Zoning Design of AP1000 Nuclear Island Building LI Yan-li;GUAN Wei;CHEN Lin;China Nuclear Power Engineering Co.
Ultimate Capacity and Influenced Factors Analysis of Reactor Containment Subjected to Internal Pressure SONG Chen-ning;HOU Gang-ling;ZHOU Guo-liang;College of Aerospace and Civil Engineering of Harbin Engineering University;SIPPR Engineering Group Co.
Parameter Optimization of the Secondary Loop Thermodynamic System of a Nuclear Power Plant LIU Cheng-yang;YAN Chang-qi;WANG Jian-jun;National Defense Key Discipline Laboratory of Nuclear Power Safety and Simulation Technology
Study on the Fire Zone Influenced by Transient Combustibles in Nuclear Power Plant ZHAO Qing-nan;YU Xin-li;China Nuclear Power Engineering Co.
Study on Control Method of the Actuators Accepting Commands from Different Classifications in Nuclear Power Plant TANG Li-xue;ZHANG Nan;FAN Jin;LI Liang;Electric and I&C Institute
Accident Analysis for Inadvertent Opening of Pressurizer Safety Valve in Sanmen NPP CHEN Jie;TANG Gang;SHAO Ge;TONG Li-li;Sanmen Nuclear Power Co.
Research and Software Development of Core Damage Assessment for Nuclear Power Plant LI Wen-jing;MA Ru-bing;TANG Jing-yu;ZHAO Bo;FU Xiao-hua;China Nuclear Power Engineering Co.
The Status Quo and Supervision of NPP Information Security from Stuxnet Attacks HU Jiang;SUN Guo-chen;ZHANG Jia-jun;HOU Qin-mai;Nuclear and Radiation Safety Center
Planning and Strategy of I&C Systems Upgrade Project in Nuclear Power Plant CAI Jun-dong;CGN Lufeng Nuclear Power Co.
Thermal Control Technologies of Electronic Devices and Their Applications on Nuclear Robots HAN Yan-long;LUAN Wei-ling;ZHANG Yan;WU Guo-zhang;GAO Feng;East China University of Science and Technology;Shanghai Jiaotong University;
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