Full-Text Search:
Home|Journal Papers|About CNKI|User Service|FAQ|Contact Us|中文
《Anhui Electric Power》 2010-03
Add to Favorite Get Latest Update

Introduction for Design of Conventional Island and BOP Grounding System in Ling Ao Nuclear Power Station Phase 2

This paper introduces the design of conventional island and BOP grounding system in Ling Ao nuclear power station phase 2 in Guangdong province.The design philosophy and detailed design method of the grounding system in view of its function and equipment are discussed which provides grounding system mode for reference in nuclear power stations and points out the possibility of optimization.
【CateGory Index】: TM862
Download(CAJ format) Download(PDF format)
CAJViewer7.0 supports all the CNKI file formats; AdobeReader only supports the PDF format.
【Citations】
Chinese Journal Full-text Database 2 Hits
1 ;Design of Grounding System in Nuclear Power Station[J];Guangxi Electric Power Engineering;2001-01
2 ;The Design and Installation of Ling Ao Nuclear Power Station in Conventional Island Earthing System[J];Shandong Electric Power;2002-03
【Co-citations】
Chinese Journal Full-text Database 10 Hits
1 ZHANG Chen-gang1,SHEN Shi-jie2,AI Hua-ning1,PENG Cui-ling1(1.Engineering Modification Center,China Nuclear Power Technology Research Institute Co.Ltd.,Shenzhen 518124,China;2.Erchong Deyang Wanlu Transportation Corp.,Deyang 618000,China);Program design about transport and storage technical scheme for long-shaft type heavy equipment[J];Journal of Electric Power Science and Technology;2008-02
2 GUAN Jian-jun,GAN Di-nan,FEI Rui-yin,CHI Zhi-yuan (Guangdong Daya Bay Nuclear Power Station,Shenzhen 518124,China);Daya Bay Nuclear Power Station 900MW Generator Unit Maximum Output Power Analysis[J];Large Electric Machine and Hydraulic Turbine;2002-05
3 ZHAO Liang,ZHONG Xiong,MAN Ruo-yan(China Nuclear Power Engineering Co.,Ltd.,Shenzhen 518124,China);Research on Type Selection of Motor-driven Constant-speed Pump and Adjustable-speed Pump for PWR Nuclear Power Plants[J];Electric Power Technology;2010-09
4 ZHENG Xiubo LIU Yun SUN Jingqiang (Guangdong Electric Design Institute,Guangzhou 510660,Guangdong Province,China);The Peak Load Regulation of Nuclear Power Plants in Guangdong Power Grid[J];Electric Power Technology;2010-Z2
5 CHEN Juan (Guangdong Electric Power Design Institute,Guangzhou 510663,Guangdong Province,China);Design of Main Steam Drain System in Ling'Ao PhaseⅡNuclear Power Plant[J];Electric Power Technology;2010-Z2
6 REN Peng-hui(China Guangdong Nuclear Power Engineering Co.,Shenzhen 518124,China);Summary of Nuclear Power Station Brushless Excitation Generator Rotor Temperature Measurement Techniques[J];Electric Power Construction;2007-01
7 WANG Zhao-peng(Guangdong Electric Power Design Institute,Guangzhou 510663,China);Application of Self-shunt Brushless Excitation System in Nuclear Power Station[J];Electric Power Construction;2010-11
8 LIU Xiaoyun,ZHANG Taiyong(China Nuclear Power Engineering Co.,Ltd.(Shenzhen),Shenzhen 518000,Guandong Province,China);Gallery Design for EPR Nuclear Power Plant[J];Electric Power Construction;2012-04
9 REN Peng-hui(China Guangzhou Nuclear Engineering Co.,Ltd.,Shenzhen 518124,China);Rotor Windings Temperature Monitoring for Nuclear Power Plant Large Brushless Excitation Generator[J];Electric Power Science and Engineering;2007-01
10 Lu Feng1,Duan Xinhui2,Liu Liping1,Jiang Dongdong1 (1.School of Control and Computer Engineering,North China Electric Power University,Baoding 071003,China; 2.Institute of Control Engineering and Computer,North China Electric Power University,Baoding 071003,China);Modeling and Simulation for Filter of Radioactive Materials in Nuclear Power Unit[J];Electric Power Science and Engineering;2011-03
China Proceedings of conference Full-text Database 4 Hits
1 REN Peng-hui,WU Chao-qun (Electrical Engineering Branch,China Nuclear Power Engineering Company,Shenzhen of Guangdong Prov.518124,China);Rotor windings temperature monitoring based on calculation for large brushless excitation generator[A];[C];2009
2 ZHANG Yan-zhao,GUO Wen-hai,TI Wen-xin (Suzhou Nuclear Power Research Institute,Suzhou of Jiangsu Prov.215004,China);Research on the monitoring technology of thermal fatigue of Nuclear reactor coolant auxiliary piping[A];[C];2011
3 WANG Qin-hu,LIU Jun-sheng,HONG Zhen-min,HOU Ye, HE Ji-qiang,ZHANG Chun-wang,SUN Wei-yi (Daya Bay Nuclear Operations &- Management Company Limited of Guangdong Prov, 518124,China);Research and practice on abnormal seal leakage rate of 100 model reactor coolant pump[A];[C];2011
4 YE Quan-liu 1 , CHENT Yan-hua 2 , DUAN Feng 1 , XIE Jian-hua (1China Nuclear Power Design Company, Ltd.,. Shenzhen of Guangdong Prov. 518057, China; 1 2 China Nuclear Power Technology Research Institute, Shenzhen of Guangdong Prov. 518026, China);The Application Study of RCM Analysis Method in Design of NPP[A];[C];2012
©2006 Tsinghua Tongfang Knowledge Network Technology Co., Ltd.(Beijing)(TTKN) All rights reserved