Sensitivity Analysis and Failure Damage Domain Identification of the Passive Containment Cooling System of an AP1000 Nuclear Reactor
نویسندگان
چکیده
The paper presents an application of a variance decomposition method for the sensitivity analysis of the thermal hydraulic (TH) model of the Passive Containment Cooling System (PCCS) of an Advanced Pressurized Reactor (AP1000). The Loss Of Coolant Accident (LOCA) is considered as the most representative accident for identifying the Failure Damage Domain (FDD) of the PCCS with respect to the individual and grouped inputs most affecting the final pressure at the end of the accidental transient.
منابع مشابه
In-containment Refueling Water Storage Tank (IRWST): In-containment passive long-term recirculation means Passive Residual Heat Removal (PRHR) utilizing Passive Residual Heat Removal Heat Exchanger (PRHR HX): Automatic Depressurization System (ADS): Internal IEs: Three major types of IEs
Safety of a nuclear power plant and its related systems are the first key issue to assure experts and the public of the safe operation of the plant. The AP1000 reactor is provided with passive safety systems which require no operator actions due to utilizing only natural forces such as gravity, natural circulation and compressed gas to achieve the safety function. In this paper the core damage ...
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