AP1000 Passive Containment Cooling System study under LBLOCA conditions using the GOTHIC code

CFD Analysis of Natural Convection on the Outer Surface of the Containment of APWR Model

“…A modern nuclear power plants such as the Advance Pressurize Water Reactor (APWR) or generation III+ reactor is equipped with a passive safety system that do not rely on equipment, in addition to the active safety systems [1]. One of the passive safety systems available on nuclear power plant reactor such as the AP-1000 reactor is the passive containment cooling system (PCCS), where naturally circulating air cools the outer surface of the containment which is used to remove decay heat released inside the containment vessel [2][3][4][5][6][7][8][9][10][11][12][13]. In the PCCS, as shown in Figure 1, the decay heat from the reactor core will be transferred to the outside of the containment vessel by the conduction mechanism through the containment wall and the natural convection mechanism on the outer surface of the containment vessel [10].…”