Full-Text Search:
Home|Journal Papers|About CNKI|User Service|FAQ|Contact Us|中文
《Power Station Auxiliary Equipment》 2012-02
Add to Favorite Get Latest Update

Handling of Overproof Horizontal Displacement of the Expansion Joint for the Reheater in Nuclear Power Station

HOU Jing-hong(Procurement Center of Complete Sets of Equipt,China Nuclear Power Engineering Co.,Ltd.,Shenzhen,Guangdong 518124,China)  
Under the working condition of the expansion joint in the drain line of moisture separator reheater(MSR for short) in Power Unit 1 in a nuclear power station,it was found that the horizontal displacement of expansion joint located in drain pipes of MSR exceeded the requirement of the design specification.If it is not promptly resolved,the operation of the unit will have risks.After the installation of Unit 2 in the power station is completed,the similar situation of horizontal displacement also exists in the MSR expansion joint.To solve these problems,multiple measures and analysis on the cause have been carried out.It is found that the problems may exist in vertical control of the expansion joint during the application assembly of similar expansion joint.which has some reference for vertical control in China.
【CateGory Index】: TL353.13
Download(CAJ format) Download(PDF format)
CAJViewer7.0 supports all the CNKI file formats; AdobeReader only supports the PDF format.
Chinese Journal Full-text Database 10 Hits
1 ;Introduction for Design of Conventional Island and BOP Grounding System in Ling Ao Nuclear Power Station Phase 2[J];Anhui Electric Power;2010-03
2 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
3 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
4 Gao Shifeng Jiamusi Electric Machine Co. Ltd;1E Class K1 Category High-voltage Three-phase Asynchronous Motor for Residual Heat Removal Pump in Nuclear Power Station[J];Electrical Machinery Technology;2010-02
5 Teng Yanling Jiamusi Electric Machine Company Limited;Three-phase Asynchronous Motor for Nuclear Power Station[J];Electrical Machinery Technology;2010-03
6 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
7 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
8 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
9 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
10 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
China Proceedings of conference Full-text Database 10 Hits
1 WANG Xin-liang,QIU Jin-rong,GONG Zi-li (Wuhan 2nd Ship Design and Research Institute,Wuhan Hubei 430000,Hubei);Numerical simulation of flow field in shellside of heat exchanger in nuclear power plant[A];[C];2009
2 YOU Wei,QIU Lin,LONG Liang (China Nuclear Power Engineering Corporation,Beijing 100840,China);Simulations of PWR spray systems by ASTEC computer code[A];[C];2009
3 GONG Zi-li,XU Jun-feng,WANG Xiao-bin (Wuhan 2nd ship design and research institute,Wuhan of Hubei Prov.430000,China);Sneak circuit analysis of chemical and volume control system[A];[C];2009
4 LIN Yuan-sheng,SONG Fei-fei,YE Shui-sheng (Wuhan 2nd Ship Design and Research Institute,Wuhan of Hubei Prov.430000,China);Study on steam generator aging management[A];[C];2009
5 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
6 XU Yao,TIAN Zhao-fei (Nuclear Power Simulation Research Center of Harbin Engineering University,Harbin of Heilongjiang Prov.150001,China);Modeling and simulation research on the moisture separator in nuclear power plant[A];[C];2011
7 GONG Zi-Li,JIA Zhen,ZHANG Li (Wuhan 2nd ship design and research institute,Wuhan of Hubei Prov.430064,China);Research on the cooperating characteristic of Regenerative and Non-regenerative Heat Exchanger in RCV[A];[C];2011
8 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
9 LI Cheng-guo~1,QU Guo-pu~1,LI Si-fang~2 (1.School of Nuclear Science and Technology,University of South China,Hengyang of Hunan Prov.421001,China; 2.School of Electrical Engineering,University of South China,Hengyang of Hunan Prov.421001,China);The simulation of ~(18)F dust transport properties in sampling channel[A];[C];2011
10 LIU Fei,JIANG Xing-wei (China Nuclear Power Engineering Co.,Ltd.,Beijing,China);Difference analysis of AP1000 and M310 units containment system[A];[C];2011
©2006 Tsinghua Tongfang Knowledge Network Technology Co., Ltd.(Beijing)(TTKN) All rights reserved