Full-Text Search:
Home|Journal Papers|About CNKI|User Service|FAQ|Contact Us|中文
《CHINESE JOURNAL OF NUCLEAR SCIENCE AND ENGINEERING》 1997-04
Add to Favorite Get Latest Update

THE SAFETY FEATURE OF HYDRAULICDRIVING SYSTEM OF CONTROL ROD FOR200MW NUCLEAR HEATING REACTOR

CHI ZONGBO WU YUANQIANG ( Institute of Nuclear Energy Technology, Tsinghua University)  
The hydraulic driving system of control rod is used as control rod drive mechanism in 200MW nuclear heating reactor . Design of this system is based on passive system, integrating drive and guide of control rod . This paper analyzes the inherent safety and the design safety of this system, with mechanism of control rod not ejecting when the pressure of pressure vessel is lost, and calculating result of core not exposing when the amount of coolant is drained by broken pipe. The results indicate that this system has good safety feature, and assures reactor safety un- der any accident conditions, providing important technology support for 200MW nuclear heating reactor with inherent Safetv feature.
【CateGory Index】: TL413.2
Download(CAJ format) Download(PDF format)
CAJViewer7.0 supports all the CNKI file formats; AdobeReader only supports the PDF format.
【References】
Chinese Journal Full-text Database 1 Hits
1 WANG Jinhua, BO Hanliang, ZHENG Wenxiang, JIANG Shengyao LIU Zhiyong, LI Jun, ZHENG Yanhua, ZHANG Youjie (Institute of Nuclear Energy Technology, Tsinghua University. Advanced Reactor Engineering and Safety, Key Laboratory of Ministry of Education of China);Experiment on Scram for HCRDS in Utmost Accident at High Temperature[J];Chinese Journal of Nuclear Science and Engineering;2002-04
【Citations】
Chinese Journal Full-text Database 2 Hits
1 Zheng Wenxiang;Dong Duo;Ma Changwen;Lin Jiagui;Wang Jiaying(Institute of Nuclear Energy Technology,Tsinghua University.Beijing);Safety Feature and Design Criteria of 5MW THR[J];Nuclear Power Engineering;1990-05
2 Hu Yuedong;Wu Yuanqiang;Liu Chengying;Cheng Yunsheng;An Jian;Dong Yonggui(Institute of Nuclear Energy Technology,Tsinghua University,Beijing);Safety Analysis and Evaluation of Hydraulic Control Rod Drive System Used for 5MW THR[J];Nuclear Power Engineering;1990-05
【Co-citations】
Chinese Journal Full-text Database 7 Hits
1 Liu Yuanzhong Cao Jianzhu(Institute of Nuclear Energy Technology, Tsinghua University, Beijing, 100084);THE CALCULATION METHOD OF ACCIDENTAL RELEASE OF RADIOACTIVITY FOR NUCLEAR DISTRICT HEATING REACTOR AND THEIR APPLICATION[J];PADIATION PROTECTION;1997-04
2 BO Han- liang, ZHENG Wen- xiang, DONG Duo, WANG Da- zhong (Institute of Nuclear Energy Technology,Tsinghua University,Beijing,100084 China);Experimental Study on Steady State Property of Hydraulic Drive Control Rod[J];Nuclear Power Engineering;2001-01
3 WANG Jin-hua,BO Han-liang,JIANG Sheng-yao,ZHENG Wen-xiang(Institute of Nuclear and New Energy Technology,Key Laboratory of Advanced Reactor Engineering and Safety of the Ministry of Education,Tsinghua University,Beijing,100084,China);Numerical Calculation of Static Holding Flow of Hydraulic Stepped Cylinder[J];Nuclear Power Engineering;2005-05
4 Chi Zongbo Wu Yuanqiang(Institute of Nuclear Energy Technology,Tsinghua University,Beijing,100084)  ;Experimental Study of Hydraulic Driving System of ControlRod Not Engendering Rod Ejection Accident[J];NUCLEAR POWER ENGINEERING;1998-03
5 Chi Zongbo Wu Yuanqiang Chen Yunxia(Institute of Nuclear Energy Technology,Tsinghua University,Beijing,100084);Study and Design of Hydraulic Driving System of Control Rod[J];NUCLEAR POWER ENGINEERING;1999-01
6 CHEN Shifeng 1, BO Hanliang 1, HU Erhong 2 (1.Institute of Nuclear Energy Technology, Tsinghua University, 2.The Department of Engineering Physics, Tsinghua University) (Manuscript received 20 August, 1999);The Resistance Coefficient Calculation on HR-200 MW Hydraulic Driving Control Rod of Chamfer and Orifice Type[J];CHINESE JOURNAL OF NUCLEAR SCIENCE AND ENGINEERING;2000-02
7 BO Hanliang, ZHENG Wenxiang, DONG Duo,WANG Dazhong (The Institute of Nuclear Energy Technology, Tsinghua University, Beijing, 100084) (Manuscript receired 15 Norember, 1999);Analysis on Step Action of Hydraulic Control Rod Driving[J];Chinese Journal of Nuclear Science and Engineering;2000-04
【Co-references】
Chinese Journal Full-text Database 3 Hits
1 Wu Yuanqiang;Yang Nianzu;Hu Yuedong;Cheng Yunsheng;Liu Chengying;Zhang Fulu(Institute of Nuclear Energy Technology,Tsinghua University,Beijing);Design and Experimental Research of Hydraulic Control Rod Drive System for 5MW THR[J];Nuclear Power Engineering;1990-05
2 ZHANG Ya-jun,WANG Xiu-zhen (INET,Tsinghua University,Beijing,100084,China);Development Progress and Prospect for lndustrial Application of the 200MW Low Temperature Nuclear Heating Reactor[J];Nuclear Power Engineering;2003-02
3 Chi Zongbo Wu Yuanqiang Chen Yunxia(Institute of Nuclear Energy Technology,Tsinghua University,Beijing,100084);Study and Design of Hydraulic Driving System of Control Rod[J];NUCLEAR POWER ENGINEERING;1999-01
©2006 Tsinghua Tongfang Knowledge Network Technology Co., Ltd.(Beijing)(TTKN) All rights reserved