To evaluate the thermal performance of a closed-loop Passive Containment Cooling System (PCCS) based on hot pipe technology under nuclear accidents, the coupled effect of three systems of reactor primary cooling circuit, containment and the PCCS is analyzed under LB-LOCA with SBO and SB-LOCA with SBO with the PCCS started one hour after the accident. The coupled analysis method is that the heat transfer power of PCCS simulated by the LOCUST model and the mass and energy releasing results obtained from the integrated analysis program for serious accidents are the inputs for containment thermal response analysis code. The results showed that in the 0∼10 hours after the accident, the containment pressure is less than the design limit of 5.20bar.a; in the middle and long term of ten more hours after the accident, the containment pressure is less than 3.50bar.a, the integrity of the containment can be ensured and the feasibility of the design of the PCCS in this paper is validated.

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