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《Nuclear Power Engineering》 2003-S1
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Nuclear Design for Qinshan Phase II NPP Project

ZHANG Zong-yao,XIAN Chun-yu,LIU Xu-dong,LI Dong-sheng RUI Min,WANG Ying-ming,SHEN Xi-rong,LI Qing (Nuclear Power Institute of China,Chengdu,610041,China)  
The general design idea, design content and the comparison results between theoretic predicted and measured values are presented in this paper. The advanced design ideas of PWR NPP in 1990s are adopted in the design. Low power density core is designed to increase core safety margin. 1/4 reload mode is used to satisfy annual reload requirement and to make full use of fuel. The reload batch burnup meets the design requirement. The fuel management mode is determined and the corresponding results are analyzed according to the design requirement. The calculated results satisfy the economic and safety requirements of cycle length, power distribution, moderator temperature coefficient, shutdown reactivity margin and discharged fuel assembly burnup, and etc. The measured results from the startup physics test and power operation of unit 1 show that the control bank worth, critical boron concentration, isothermal temperature and core power distributions fit well to predicted values.
【CateGory Index】: TL352
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【References】
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【Co-references】
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1 Tao Shaoping;Digital Inverse Kinetics Method with Eliminating the Space Effect[J];Nuclear Power Engineering;1985-01
2 Zhang Zongyao Li Datu Yao Dong Cheng Heping (Nuclear Power Institute of China, Chengdu, 610041) Xie Zhongsheng Yin Banghua (Xi'an Jiaotong University, 710049);TPFAP——a Code Package for LWR Fuel Assembly Calculation[J];Nuclear Power Engineering;1993-02
3 ZHOU Song1,DAI Jing-ming1,ZHANG Zhi-jiang2 (1. Harbin Institute of Technology,Harbin,150001,China;2. Harbin Engineering University,Harbin,150001,China);The Realization of Remove Function System in Nuclear-Power Equipment Simulator[J];Nuclear Power Engineering;2002-04
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5 MIN Yuan-you,HUANG Yun (Nuclear Power Institute of China,Chengdu,610041,China);Design of the Reactor and Reactor Coolant System for Qingshan Phase II NPP Project[J];Nuclear Power Engineering;2003-S1
6 ZUO Wen,YAN Yu-hui (Nuclear Power Institute of China, Chengdu, 610041, China);Design of Rod Control and Rod Position System in Qinshan Phase II NPP Project[J];Nuclear Power Engineering;2003-S1
7 YANG Lai-sheng,ZONG Gui-fang ,HU Jun (Nuclear Power Institute of China,Chengdu, 610041, China);Reactor Hydraulic Simulation Test Study of Qinshan Phase II NPP Project[J];Nuclear Power Engineering;2003-S1
8 LI Wen-ping,ZHANG Fan,LU Yu-chuan,XIE Zhong (Nuclear Power Institute of China,Chengdu,610041,China);Design of the In-core Instrumentation System for Qinshan Phase II NPP Project[J];Nuclear Power Engineering;2003-S1
9 ZHAO Shan-de (Nuclear Power Institute of China,Chengdu,610041,China);Instrumentation and Control of Reactor and Coolant System for Qinshan Phase II NPP Project[J];Nuclear Power Engineering;2003-S1
10 LIU Jiong,ZHANG Fan,ZHANG Rui,ZHANG Ying (Nuclear Power Institute of China,Chengdu 610041,China);Design of Reactor Control System in Qinshan Phase II NPP Project[J];Nuclear Power Engineering;2003-S1
【Secondary References】
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1 ZHAO Yu CAO Xin-rong ZHAO Qiang (College of Nuclear Science and Technology,Harbin Engineering University,Harbin of Heilongjiang Prov.150001,China);Verification of results of core physics on-line simulation by NGFM code[J];Chinese Journal of Nuclear Science and Engineering;2008-01
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