Development of a thermal-hydraulic analysis software for the Chinese advanced pressurized water reactor

被引：16

作者：

Wu, Y. W. ^{[1
]}

Su, G. H. ^{[1
]}

Qiu, S. Z. ^{[1
]}

Zhuang, C. J. ^{[1
]}

机构：

[1] Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Dept Nucl Sci & Technol, Xian 710049, Peoples R China

来源：

NUCLEAR ENGINEERING AND DESIGN | 2010年 / 240卷 / 01期

关键词：

HEAT-TRANSFER;

D O I：

10.1016/j.nucengdes.2009.10.020

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：

A point reactor neutron kinetics model, a drift-flow U-tube steam generator model, a non-equilibrium three-region pressurizer model and other models were established and a transient analysis code with Visual Fortran 6.5 has been developed to analyze the thermal-hydraulic characteristics of the Chinese advanced pressurized water reactor (AC-600). Visual input, real-time processing and dynamic visualization output were achieved with Microsoft Visual Studio.NET 2003, which greatly facilitate applications in the engineering. The software were applied to analyze the transient thermal-hydraulic characteristics of the loss of feed-water accident, the double loops loss-of-flow accident, the reactivity insertion accident, the sudden increase of feed-water temperature accident and the loss of offsite power accident for the Qinshan nuclear power plant in China. The obtained analysis results are significant to the improvement of design and safety operation of the plant. (C) 2009 Elsevier B.V. All rights reserved.

引用

页码：112 / 122

页数：11

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