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In the advanced pressurized water reactor nuclear power plant design, the passive residual heat removalsystem is adopted. This system is composed of the secondary side of steam generator, air cooler and air loop whichconsists of the air cooling tower and atmosphere environment. Wall-air heat exchanging correlation equation is added tothe RELAP5 Code. The modified code is used to simulate the AC600 PWR nuclear power plant transient behavior withPassive Residual Heat Removal System (PRHR) in micro-circulation start-up mode after the blackout accident occurs.The calculation results show that the higher the chimney or the larger the air cooler heat transfer area, the more the heatremoval capacity of PRHR system. The computational results are consistent with the theoretical analyses.[
In the advanced pressurized water reactor nuclear power plant design, the passive residual heat removalsystem is adopted. This system is composed of the secondary side of a steam generator, air cooler and air loop whichconsists of the air cooling tower and atmosphere environment. Wall-air heat The modified code is used to simulate the AC600 PWR nuclear power plant transient behavior with Passive Residual Heat Removal System (PRHR) in micro-start start-up mode after the blackout accident occurs. The calculation results show that the higher the chimney or the larger the air cooler heat transfer area, the more the heat capacity value of PRHR system. The computational results are consistent with the theoretical analyzes. [