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Nuclear Power Engineering
FQ: bimonthly
AD of Publication: China
Lanuage: English
ISSN: 0258-0926
CN: 51-1158/TL
YP: 1980
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2017 -04
Catalog
Turbulence Model Evaluation in Circular Pipe of Supercritical Water Based on Statistical Method Leng Jie;Zang Jinguang;Yan Xiao;Li Yongliang;Huang Yanping;Nuclear Power Institute of China;
Derivation and Preliminary Verification of Algorithm for Homogenized Flux Reconstruction Ming Pingzhou;Lu Wei;Cao Xingdi;Xia Bangyang;Liu Dong;Yu Hongxing;Sun Yufa;Science and Technology on Reactor System Design Technology Laboratory
Numerical Simulation Study on Containment Hydrogen Deflagration Risk under Severe Accident Yang Fan;S.Kudriakov;Yu Hongxing;Deng Jian;Li Songwei;Zeng Wei;Liu Songtao;Science and Technology on Reactor System Design Technology Laboratory
Numerical Computation Verification of Erosion Behaviours of Reactor Cavity with High Gas-content Concrete in Homogeneous Melt Pool Configuration Ma Jian;Yan Xiao;Zan Yuanfeng;Zhuo Wenbin;CNNC Key Laboratory on Reactor Thermo-Hydraulics and Safty Technology
Development of a γ-Ray Monitoring System Based on Local Area Network Li Mingfu;Jin Changjiang;Yuan Yonggang;Chengdu Aeronautic Vocational and Technical College;Institute of Nuclear Physics and Chemistry
Experimental Study of Passive Injection System Operation Characteristics under Different DVI Break Size Conditions Huang Zhigang;Peng Chuanxin;Zhang Yan;Li Yang;Zan Yuanfeng;Zhuo Wenbin;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology
Design Calculation of Carbon Delay Bed Zhu Bonan;Liu Yu;Wang Yiwei;China Nuclear Power Engineering Co.Ltd.;
Analysis of Natural Circulation Flow Characteristics under External Vessel Cooling of In-Vessel Retention Yan Xiao;Hu Qiang;Huang Shanfang;Yu Junchong;Li Yang;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology
Transient Analysis on Overpower and Loss of Heat Sink of A Small Natural Circulation Lead-Cooled Fast Reactor Shi Kangli;Zhang Xilin;Chen Hongli;University of Science and Technology of China;
Experiment Study on Thermal Erosion of CF2 Series Fuel Assemblies Tian Xuelian;Nie Changhua;Yu Qinglin;Rong Xiaohong;Xu Changzhe;Li Shuo;Chen Xungang;Nuclear Power Institute of China;
CFD Simulation and Synergy Field Analysis of Two Typical Mixing Vanes of Space Grad Dai Xudong;Chen Weihong;Yang Lixin;Nuclear Power Institute of China;School of Mechanical
Transient Study on Characteristics of Power Generation by FHR Coupling with Air Brayton Turbine Cycle Ruan Jian;Zou Yang;Li Minghai;Zhou Bo;Zhu Guifeng;Xu Hongjie;University of Chinese Academy of Sciences;Shanghai Institute of Applied Physics
Effect of Damping Parameters on Seismic Analysis of Nuclear Reactor Coolant Loop Wang Qing;Fang Yonggang;Chu Qibao;Lu Yan;Xu Yu;Li Hailong;Wen Jing;Nuclear and Radiation Safety Center
Shaking Table Test for Evaluation of Seismic Behavior of Nuclear Power Plants on Non-Rock Site Li Xiaojun;Wang Xiaohui;He Qiumei;Liu Aiwen;Institute of Geophysics
Study on Control Rod Device Mechanism Impacting on Missile Shield Plate Ye Xianhui;Zheng Bin;Jiang Naibin;Wu Wanjun;Xu Pei;Key Laboratory of Science and Technology on Reactor System Design Technology
Comparative Study of Welding Procedure Qualification Standard between NB/T 20002 and ASME-Ⅸ in Nuclear Power Industry Wang Yuxin;Li Zhe;Dong An;Wang Heng;China Nuclear Power Engineering Co.Ltd.;
Effect of Different Designs for Loss of LBA on Core Damage Frequency Yang Jian;Bei Junjuan;China Nuclear Power Engineering Co.Ltd.;
Improvement of AMS Calibration Equipment in Radiation Protection Area Li Xiaoning;Ren Xueming;Zhou Bing;Chen Haiyan;Zhang Kai;Taishan Nuclear Power Joint Venture Co.Ltd.;
Analysis and Application of Load Change Rate Algorithm For CPR1000 Nuclear Power Plant Lan Bing;Meng Qingjun;Yang Jingli;Cai Yawei;China Techenergy Co.Ltd;
Test of Air Cooling Characteristics of Control Rod Drive Mechanism for ACP100 Tian Xuelian;Rong Xiaohong;Zhuo Wenbin;Xu Changzhe;Wang Yunsheng;Zhang Yang;Xu Shijie;Zhang Lin;Ma Xinguang;Nuclear Power Institute of China;
Development of Intelligentized Accident Source Term Evaluation Code Yu Hong;Li Lan;Zhu Jianping;He Fan;Science and Technology on Reactor System Design Technology Laboratory
Thermal Optimization and Design for Irradiation Rig of Multi-Fuel Assembly Xu Taozhong;Xiang Yuxin;Wang Hao;Deng Caiyu;Liu Shuiqing;Sun Shouhua;Nuclear Power Institute of China;
Investigation on Methodology of Coastdown Analysis and Design for Reactor Coolant Pump Zhong Yun;Liu Yi;Zhou Wenxia;Xia Di;Shanghai Nuclear Engineering Research and Design Institute;
Analysis of Rigging Lifting for AP1000 Containment Vessel Module by Finite Element Method Li Tuo;Sanmen Nuclear Power Co.Ltd.;
Kinematic Verticality Adjustment Technology for Refueling Machine Inner Mast Shen Yabo;Li Tao;Guo Keke;Sanmen Nuclear Power Co.Ltd.;
Study on Availability Factor Model Promotion in Nuclear Power Plants Chen Wen;Yang Xiaohu;Jiang Hong;Suzhou Thermal Power Research Institute;
Cause Analysis and Suggested Solutions for Reactor Coolant Pump Motor Oil Leakage Jiang Hong;Zhou Jing;Jiang Xiaomao;He Jinsong;Deng Xiao;Mao Yuanfan;Science and Technology on Reactor System Design Technology Laboratory
Research on Eddy Current Test Precision for the Position of Anti-Vibration Bars on Steam Generator Tubes Ma Qiang;Kong Yuying;Gu Bo;Lu Ji;Wang Xiaogang;CGNPC Inspection Technology Company
Failure Analysis and Overall Maintenance of Recirculation Cooling Water System Heat Exchanger of Third Qinshan Nuclear Power Plant Gong Daitao;Jiang Feng;Wang Xin;Cheng Jifang;Hu Jianqun;CNNC
Research of Test Scenario of T2 Response Time of Reactor Protection System Xu Yong;Hu Wenyong;Wang Yan;Lin Yan;You Bing;Fujian Fuqing Nuclear Power Co.Ltd.;
Research and Development of Service Life and Replacement Strategy for Neutron-temperature Measurement Channel Zhang Qi;Instrument & Control Office
Non-Linearity Research on Ultrasonic Inaccessible Zones for Inlet to Shell Weld of RPV Hong Maocheng;Wu Jianrong;Yuan Shuxian;Ma Guanbing;Shen Liang;Sun Jiawei;Zhu Chuanyu;CGNPC Inspection Technology Co.Ltd.;
Measurement and Calculation of Heat Generation Rate of Stainless Steel in a Research Reactor Si Junping;Tong Mingyan;Yang Wenhua;Zhang Liang;Nie Liangbing;Zhang Ping;Nuclear Power Institute of China;
Uncertainty Analysis of Manufacturer Parameters Impact on TVS-2M Fuel Rod Performance in Reactor Jiang Xiaochuan;Song Zifan;He Kai;Yang Nirong;China Nuclear Power Engineering Co.Ltd.;
Microstructure of Heat-Affected Zone in a Weld Joint between Alloy 690 and Alloy 152 Nie Shuhong;Liang Zhengqiang;China Institute of Atomic Energy;
Simulation Research on Effect of Processing Parameter on Hot Rolling of Fuel Plate Yang Hongyan;Peng Xiaoming;Ding Shurong;Guo Zhen;Kong Xiangzhe;Science and Technology on Reactor Fuel and Materials Laboratory
Study on Microstructure and Mechanical Properties of Zr-Sn-Nb Alloys Thin Sheet Weld Li Shunping;Peng Qian;Yang Zhongbo;Chen Le;Li Weijun;Science and Technology on Reactor Fuel and Materials Laboratory
Study on Stress Corrosion Cracking of Welded Joint with Inconel 690 and 321 Stainless Steel Sun Yongduo;Xiong Ru;Qiu Shaoyu;Song Yiyang;Wang Jiamei;Zhang Lefu;Science and Technology on Reactor Fuel and Materials Laboratory
Numerical Verification of KYLIN-Ⅱ Code Based on IAEA Plate Fuel Benchmark Lu Wei;Yin Qiang;Chen Dingyong;Chai Xiaoming;Tu Xiaolan;Science and Technology on Reactor System Design Technology Laboratory
Investigation on Pressure Drop Oscillation in Two-Phase Natural Circulation system Peng Chuanxin;Zhuo Wenbin;Zan Yuanfeng;Xu Jianjun;Lu Xiaodong;Huang Yanping;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology
2017 Issues:  [01] [02] [03] [S1] [04]
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