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非能动余热排出系统瞬态分析
引用本文:臧希年,黄冰,郭卫军.非能动余热排出系统瞬态分析[J].清华大学学报(自然科学版),2000,40(10):20-23.
作者姓名:臧希年  黄冰  郭卫军
作者单位:清华大学,工程物理系,北京,100084
摘    要:针对现有的一些大型电站系统分析程序在处理非能动余热排出系统不方便的问题 ,开发了一种简便的分析工具— SGSPRHR程序 ,用来分析全厂断电事故发生后反应堆3个回路的瞬态行为。该程序对汽水回路使用一维漂移流模型 ,而对一回路和空气回路使用单相流体模型 ,采用非线性二阶算法求解刚性方程组。计算结果表明 :烟囱高度增加 ,空冷器面积增大 ,冷热芯高差增加均使系统的排热能力增强。计算结果与理论分析相一致。

关 键 词:核动力堆  自然循环  余热排出  瞬态分析
修稿时间:1999-09-09

Transient analyses of passive residual heat removal system
ZANGXinian,HUANGBing,GUOWeijun.Transient analyses of passive residual heat removal system[J].Journal of Tsinghua University(Science and Technology),2000,40(10):20-23.
Authors:ZANGXinian  HUANGBing  GUOWeijun
Abstract:The passive residual heat removal system often can not be easily analyzed with existing nuclear power plant analysis codes. Therefore a simple and convenient code SGSPRHR was developed to analyze the transient behavior of the three loops of a power plant when the plant under goes a total loss of power accident. A one dimensional drift flux mixture flow model was used for the analysis of the steam water loop, with a single phase fluid model applied to the single phase flow in the primary system and the air loop. A non linear second order algorithm was used to solve the stiff equations. The calculated results show that increasing the chimney height, the air cooler area, or the height difference between steam generator and the air cooler will increase the heat removal capacity of the PRHR system. The computational results are consistent with theoretical analyses.
Keywords:nuclear  power reactor  natural circulation  residual heat removal  transient analysis  
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