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《CHINESE JOURNAL OF NUCLEAR SCIENCE AND ENGINEERING》 1995-03
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A CALCULATION MODEL OF FLOW CHARACTERISTIC OF COOLANTPUMP FOR NUCLEAR REACTOR SYSTEM

GUO YUJUN; ZHANG JINLING; QIU SUIZHENG SU GUANGHUI; JIA DOUNAN; YU ZHENWAN(Xi’an Jiaotong University)  
In pressurized water reactor(PWR),the heat is removed by circulation of ccolant in primarylcops. The ccolant flow is attributed to the head of main circulation pump generally,and thenatural circulation head of ccolant specially. Under these conditions,the pump characteristics areimportant to reactor safety. In this paper, a calculation method of pump flow characteristics understeady and transient conditions for a PWR is presented according to four-quadrant pumpcharacteristic. This method is convenient for practical calculation with results in good agreementwith those of Relap5/MOD2 code.
【CateGory Index】: TL343
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【References】
Chinese Journal Full-text Database 3 Hits
1 CHEN Xiang-yang,YUAN Dan-qing,YANG Min-guan,YUAN Shou-qi(Jiangsu University,Zhenjiang 212013,China);Study on Fluid-Solid Coupling Heat Transfer in Reactor Coolant Pump of one 300MWe Nuclear Power Plant[J];Fluid Machinery;2010-01
2 Tian Wenxi~1,Qiu Suizheng~1,Guo Yun~1,Su Guanghui~1,Jia Dounan~1,Liu Tiancai~2,Zhang Jianwei~2 (1.School of State key Laboratory of Multiphase Flow in Power Engineering, Xi′an Jiaotong University, Xi′an 710049, China; 2 Department of Reactor Engineering Design, China Institute of Atomic Energy, Beijing 100080, China);Development of a Transient Thermal-Hydraulic Analysis Code for China Advanced Research Reactor[J];Journal of Xi'an Jiaotong University;2005-03
3 LIU Xia-jie1,LIU Jun-sheng2,WANG De-zhong1,YANG Zhe2,ZHANG Ji-ge1(1.Nuclear Science and Engineering College,Shanghai Jiao Tong University,Shanghai 200240,China;2.Daya Bay Nuclear Power Operations and Management Co.,Ltd.,Shenzhen 518124,China);Test Study on Safety Features of Station Blackout Accident for Nuclear Main Pump[J];Atomic Energy Science and Technology;2009-05
【Citations】
Chinese Journal Full-text Database 1 Hits
1 Zhang Senru (Nuclear Power Institute of China, Chengdu, 610041);Transient Behavior Calculation for Reactor Coolant Circulation Pump[J];Nuclear Power Engineering;1993-02
【Co-citations】
Chinese Journal Full-text Database 10 Hits
1 Li Ziping;Zhu Jizhou;Yu Baoan;Calculation on Fission Product Transport and Release to Environment During PWR Accident[J];Nuclear Power Engineering;1988-05
2 LI Hai-tao YU Tao (University Of South China,Hengyang of Hunan Prov.421001,China);A Micro-current Amplifier Used for Neutron Fluctuations Characteristics Measurement of"Venus 1#"for ADS[J];Nuclear Electronics & Detection Technology;2008-06
3 Lin Xiaoling Zhang Guiwen Sun Peiquan;Estimated Inventory of Radionuclides in Marine Reactors[J];;1997-04
4 XIE Hai-yan, CAI Qi, YU Lei(College of Naval Architecture and Power,Naval University of Engineering,Wuhan430033,China);Research of processing measures on steam generator feedwater decrease events in marine nuclear power plant[J];Ship Science and Technology;2009-11
5 ZHANG Long-fei ZHANG Da-fa WANG Shao-mingSchool of Naval Architecture and Power Naval University of Engineering Wuhan 430033;Influence of rotational inertia on transient performance of the main pump of marine nuclear power plant[J];Ship & Ocean Engineering;2005-02
6 ZHANG Long-fei ZHANG Da-fa WANG Shao-mingCollege of Naval Architecture and Marine Power Naval University of Engineering Wuhan 430033;The feasibility study on frequency conversion timing scheme of main coolant pump[J];Ship & Ocean Engineering;2005-05
7 HU Zhi-min WANG Wei MENG Hai-boWuhan Second Ship Design and Research Institute Wuhan 430064;Dynamic analysis of water hammer to feed water system of the nuclear power plant[J];Ship & Ocean Engineering;2007-03
8 Ren Dexi,Hu Bo (Midsouthern Institute of Technology Hunan 421001);Primary Research on Analysis Methods and Evaluation Criteria of Safety in Nuclear Power Plants[J];Chinese Ergonomics;1996-05
9 Ren Dexi; Hu Bo(Midsouthern Institute Of Technology Hunan 421001);Primary Research on Analysis Methods and Evaluation Criteria of Safety in Nuclear Power Plants[J];CHINESE ERGONOMICS;1996-03
10 Dong Zhiqiang Shi Xinsheng (Auto-management College of the PLA, Bengbu 233011) Wu Xiaobo (Zhejiang University, Hangzhou 310027);Efficient Evaluation and Application of Decision Influence Diagrams[J];SYSTEMS ENGINEERING ---THEORY & PRACTICE;1996-10
China Proceedings of conference Full-text Database 1 Hits
1 CHEN Deng-ke ZHANG Da-fa (Ship and Power Eng.College,Naval Univ.of Engineering Wuhan Hubei 430033);Research on Distributed and Intelligent Decision-Making Support System for Nuclear Power Operation[A];[C];2007
【Co-references】
Chinese Journal Full-text Database 10 Hits
1 LI Zhi-zhao1,YAO Da-kun2,CHAI Xin-hua2 (1.Hadian National Engineering Center-Power Equipment Co.Lit,Harbin 150040,Ch ina; 2.Harbin Institute of Large Electric Machinery,Harbin 150040,China);Rotating Shafts Vibration Analysis of Nuclear Power 300MW Coolant Pump Motor[J];Large Electric Machine and Hydraulic Turbine;2001-03
2 SUN Zixiang; WU Yulin; XUE Dunsong(University of petroleum Beijing 100083) (Tsinghua University, Beijing 100084);NUMERICAL SIMULATION OF TURBULENT FLOW IN A CENTRIFUGAL PUMP IMPELLER[J];JOURNAL OF ENGINEERING THERMOPHYSICS;1996-S1
3 LI Chun ZHANG Helin (Nuclear and Radiation Safety Center,SEPA,Beijing 100082,China);Development and Application Prospect of PSA[J];Nuclear Safety;2007-01
4 OU Yang-yu1,WANG Da-sheng2(1.Chinese nuclear industry group company,Beijing 100822;2.North China electric power university school administration office,Beijing 102206);International nuclear power application and its prospect forecast and our country nuclear electricity development[J];Journal of North China Electric Power University(Natural Science Edition);2007-05
5 Huang Chengming;The Development Tendency of Reactor Coolant Pumps Used in LWR[J];Nuclear Power Engineering;1988-02
6 Zhang Senru (Nuclear Power Institute of China, Chengdu, 610041);Transient Behavior Calculation for Reactor Coolant Circulation Pump[J];Nuclear Power Engineering;1993-02
7 Deng Shao wen (Nuclear Power Institute of China,Chengdu 610041,China);Calculation of Transient of the Reactor Coolant Pumps for Qinshan Phase Ⅱ Nuclear Power Plant[J];Nuclear Power Engineering;2001-06
8 LU Qun-xian (Huazhong Science Technology University,Wuhan 430074,China);Reactor Primary Pumps Dynamic Balancing Test[J];Nuclear Power Engineering;2002-03
9 ZHANG Jing-cai,ZHOU Yue-min (Key Laboratory of Nuclear Reactor System Design Technology,Nuclear Power Institute of China,Chengdu,610041,China);Standard Problem of Nuclear Power Localization in China[J];Nuclear Power Engineering;2004-04
10 HUANG Anting ( Hangzhou Hangyang Share Co Ltd, Hangzhou, 310004, Zhejiang, China );A Comparison Between the Pressure Vessel Standard of China and ASME Code[J];Chemical Engineering & Machinery;2003-05
【Secondary References】
Chinese Journal Full-text Database 1 Hits
1 TIAN Wen-xi1, QIU Sui-zheng1, SU Guang-hui1, JIA Dou-nan1, LIU Xing-min2, ZHANG Jian-wei2 (1. State Key Laboratory of Multi-Phase Flow in Power Engineering, Xi’an Jiaotong University, Xi’an, 710049,China; 2. China Institute of Atomic Energy, Beijing, 102413, China);Development and Validation of Thermal-Hydraulic and Safety Analysis Code for CARR (TSACC)[J];Nuclear Power Engineering;2009-01
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