Transient analyses of the passive residual heat removal system

被引：1
|
作者：
Zang, XN [1 ]
Guo, WJ [1 ]
Huang, B [1 ]
Shen, SF [1 ]
机构：
[1] Tsing Hua Univ, Dept Engn Phys, Beijing 100084, Peoples R China
来源：
NUCLEAR ENGINEERING AND DESIGN | 2001年 / 206卷 / 01期
关键词：
D O I：
暂无
中图分类号：
TL [原子能技术]; O571 [原子核物理学];
学科分类号：
0827 ; 082701 ;
摘要：
The steam generator secondary residual heat removal system is a new design with three-fold natural circulation loop. It is the candidate of the safeguard systems of next generation pressurized water reactor design in China. This paper presents the development of a program, which would be used in the system design. One-dimensional drift flux mixture flow model is used for analysis of the steam water loop. whereas single-phase fluid model is applied to single flow in primary system and air loop. Based on the mathematical model. the code SGSPRHR has been developed. The transient analyses, when station black out accident happens. have been made. Sensitivity study results have also been given. The calculated parameter variation trends are reasonable. (C) 2001 Published by Elsevier Science B.V. All rights reserved.
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收藏
页码：105 / 111
页数：7
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