Sensitivity Analysis and Failure Damage Domain Identification of the Passive Containment Cooling System of an AP1000 Nuclear Reactor

Francesco Di Maio , Giancarlo Nicola (1) , Yu Yu (2) , Enrico Zio (3, 4, 5)

1 Dipartimento di Energia [Milano]
2 IBMP - Institut de biologie moléculaire des plantes
3 SSEC - Chaire Sciences des Systèmes et Défis Energétiques EDF/ECP/Supélec
4 LGI - Laboratoire Génie Industriel - EA 2606
5 CentraleSupélec

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.

Mots clés: AP1000; Variance Decomposition; Failure Damage Domain; Passive Systems Reliability

Domaines: Sciences de l'ingénieur [physics]

Francesco Di Maio, Giancarlo Nicola, Yu Yu, Enrico Zio. Sensitivity Analysis and Failure Damage Domain Identification of the Passive Containment Cooling System of an AP1000 Nuclear Reactor. Probabilistic Safety Assessment and Management Conference, 2014, Honolulu, United States. ⟨hal-01787161⟩