Abstract

A passive containment cooling system (PCCS) has been designed to effectively remove the energy released to a containment by using condensation heat during a loss of coolant accident (LOCA) in a nuclear reactor. During the past few years, thermal-hydraulic performance of the PCCS has been analyzed using system scale codes, MARS and GOTHIC codes. In this work, thermal-hydraulic performance of the PCCS was analyzed again using the MARS-CUPID coupled code, which is a combinded code of the system scale and component scale, respectively. For a more realistic simulation, we modified Uchida correlation to take into account the effect of pressure in the MARS-CUPID coupled code. The simulation result showed the peak pressure of 4.31 bar, which is similar to the peak pressure obtained using the GOTHIC code. In this study, thermal-hydraulic performance of the PCCS considering uncertainty parameters, such as mass&energy release, heat transfer coefficient, and heat sink area, is also discussed.

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