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.
Talk to us
Join us for a 30 min session where you can share your feedback and ask us any queries you have
Schedule a callDisclaimer: All third-party content on this website/platform is and will remain the property of their respective owners and is provided on "as is" basis without any warranties, express or implied. Use of third-party content does not indicate any affiliation, sponsorship with or endorsement by them. Any references to third-party content is to identify the corresponding services and shall be considered fair use under The CopyrightLaw.
