AC600核电站断电事故分析

Blackout Accident Analyses of AC600Nuclear Power Plant

我国先进压水堆核电站设计中采用了非能动余热排出系统,它由蒸汽发生器及空气冷却器构成的汽水回路和空气回路组成。本文在RELAP5程序中补充了空气壁面换热结构关系式,分析先进的压水堆核电站(AC600)全厂断电事故后的瞬态行为。结果表明:烟囱高度增加。

In the advanced pressurized water reactor nuclear power plant design,the passive residual heat re-moval(PRHR)system is adopted.This system is composed of the secondary side of steam generator,air cooler and air loop which consists of the air cooling tower and atmosphere environment.Wall-air heat exchanging correla-tion equation is added to the RELAP5code.The modified code is used to simulate the AC600PWR nuclear power plant transient behavior with Passive Residual Heat Removal System(PRHR)in micro-circulation start-up mode af-ter the blackout accident occurs.The calculation results show that the higher the chimney or the more the air cool-er heat transfer area,the more the heat removal capacity of PRHR system.The computational results are consis-tent with theoretical analyses.