In the advanced pre ssurized water reactor nuclearpowerplant design,the pas sive res idual heat removals ystem is adopted.This system is composed of the secondary side ofsteam generator,air coo ler and air loop whichc...In the advanced pre ssurized water reactor nuclearpowerplant design,the pas sive res idual heat removals ystem is adopted.This system is composed of the secondary side ofsteam generator,air coo ler and air loop whichconsis ts of the air cooling tower and atmosphere environment.Wall-air heat exchanging corre lation equation is added tothe RELAP5 Code.The modified code is used to s imulate the AC600 PWR nuclearpower plant trans ient behavior withPas sive Res idualHeat RemovalSystem(PRHR)in micro-circulation start-up mode after the bla ckout accident occurs.The calculation res ults show that the higher the chimney or the larger the air cooler heattransfêr area,the more the heatremoval capacity of PRHR sys tem.The computationalresults are cons istent with the theoreticalanalyses.展开更多
文摘In the advanced pre ssurized water reactor nuclearpowerplant design,the pas sive res idual heat removals ystem is adopted.This system is composed of the secondary side ofsteam generator,air coo ler and air loop whichconsis ts of the air cooling tower and atmosphere environment.Wall-air heat exchanging corre lation equation is added tothe RELAP5 Code.The modified code is used to s imulate the AC600 PWR nuclearpower plant trans ient behavior withPas sive Res idualHeat RemovalSystem(PRHR)in micro-circulation start-up mode after the bla ckout accident occurs.The calculation res ults show that the higher the chimney or the larger the air cooler heattransfêr area,the more the heatremoval capacity of PRHR sys tem.The computationalresults are cons istent with the theoreticalanalyses.
