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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
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2017 -01
Catalog
The Dose Calculation Method Research for the Criticality Accident Alarm System Instrument SHAO Zeng;YI Xuan;HUO Xiao-dong;China Nuclear Power Engineering Co;
Improvement of CANDU Reactor Power Measurement and Control XIONG Wei-hua;CNNP Nuclear Power Operations Management Co.
How to Choose Operation Conditions of Radioactive Liquid Waste Evaporation Processing System TANG Yang;ZHANG Yong-kang;LI Zhen-chen;Nuclse power institute of China;
The Research on the Calculation of Break Size in LOCA and SGTR LIU Xin;CHEN Xian-long;GAO Jing-dong;China Nuclear Power Design Company Ltd.;Daya Bay Nuclear Power Operations and Management Co.
Research on Thorium-uranium Breeding Recycle in Heavy Water Reactors YANG Bo;SHI Jian-feng;BI Guang-wen;TANG Chun-tao;Shanghai Nuclear Engineering Research and Design Institute;
Research and Design of the Complete Counter Current Mixer-settler for Nuclear Fuel Reused Instrument and Control System Based on Foundation Fieldbus MA Shi-hai;ZHANG Bo;LI Xiao-wei;China Nuclear Power Engineering Co.
Research and CFD Analysis of the Ventilation System in Dry Interim Storage Building of Vitrification Plant for Dealing with Spent Fuel WEI Gang;WANG Lu;Architecture station of CNPE;
Fuel Cost Analysis for Fission Layer of Fusion-Fission Hybrid Reactor for Energy LIU Guo-ming;SHAO Zeng;China Nuclear Power Engineering Co.Ltd.;
Study of Water Hammer Characteristics for Integral Reactor Primary Circuit of 900 MW PWR XU Wei-hui;LIANG Cheng-sheng;WANG Wei-shu;LU Tong;GUO Hui-jun;Institute of Thermal Engineering Research
Safety Guaranteeing for Storage of High level Liquid Wastes LI Ke-ping;Sichuan Environmental Protection Engineering Co.
The Research on Decoupling Control in Pressure and Water Level of PWR Pressurizer QIAN Hong;ZHOU Lei;FANG Zhen-lu;Shanghai University of Electric Power;
The Eddy Current Testing Method and Application in the Heat Transfer Tube Fouling of Steam Generator YAO Chuan-dang;XIA Qing-you;WANG Jia-jian;ZENG Yu-hua;LIU Xin;China Nuclear Power Operation Technology Corporation;
Research of Shape Measurement and Control System for Fast Reactor Assembly Based on Virtual Instrument Technology LIU Yun-yan;SUN Yu;SHEN Feng-yang;WU Chun-liang;LI Xing;GAO Ji-ning;GU Chun-xing;LI Guo-cai;China Institute of Automatic Energy;State Nuclear Power Technology Research & Development Centre;
Analysis on the Construction Technology of CB20 Structure Module AN Wen-bin;CHEN Wei-xing;WEI Jun-ming;Sanmen nuclear power Co.
Analysis of Intervening Measures About Actuators Act-refused and Act-error During Safety Injection Test YAN Ming-jing;ZHU Zeng-pei;GAO Yuan;China Nuclear Power Engineering Co.
The Study of HRA Methods in Level 2 PSA ZHANG Jia-jia;LIU Jing-gong;XIAO Jun;YANG Zhi-yi;CHONG Yi-min;Nuclear and Radiation Safety Center;China Nuclear Power Engineering Co.
Study on Character of Core Barrel Beam Mode Vibration During PWR Refueling Cycle YANG Tai-bo;LIU Cai-xue;LUO Ting;JIAN Jie;Nuclear Power Institute of China;
Development and Application of Fusion Database FusionDB WANG Fang;HU Li-qin;LONG Peng-cheng;ZOU Jun;LI Chun-jing;WANG Jin;SHANG Lei-ming;SONG Jing;CHENG Meng-yun;YU Sheng-peng;HAO Li-juan;HE Tao;NIE Miao;XUE Feng;HUANG Qun-ying;WU Yi-can;FDS Team;Key Laboratory of Neutronics and Radiation Safety
Researchand Verification of Activation Calculations Based on Chebyshev Rational Approximation Method ZHANG Bin-hang;HAO Li-juan;GE Peng;SONG Jing;PENG He;Institute of Nuclear Energy Safety Technology
Study on the Method of Parameters Optimization for Tokamak Fusion Reactor Core Based on GA SUN Lin;CHEN De-hong;WANG Ming-huang;JIANG Jie-qiong;Key Laboratory of Neutronics and Radiation Safety
Pressurizer Room Hydrogen Risk Analysis of M310 Nuclear Power Plant Under Severe Accidents LI Jing-jing;WANG Hui;SHI Xue-yao;China Nuclear Power Engineering Co.
Study on Entry Conditions for Serve Accident Management Guideline FENG Shang-ren;TONG Li-li;School of Mechanical Engineering
Study on Dose Characteristics of CAP1000 Main Control Room in Accident Condition ZHANG Shan-shan;FU Ya-ru;SUN Da-wei;MEI Qi-liang;Shanghai Nuclear Engineering Research and Design Institute;
Impact Analysis of CPR1000 Nuclear Power Plant Outage One CRF Pump at Low Power WU Jin-guo;WANG Jian-guo;Liaoning HongYanhe Nuclear Power Co.
Root Cause Analyses for the Electro-Magnetic Interference in NPP also the Whole Process Defenses Strategy PANG Song-tao;XIONG Guo-hua;ZHOU Zhou;China Nuclear Power Technology Research Institute;
2017 Issues:  [01] [02] [03] [04]
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