The Modular Accident Analysis Program for CANDU (MAAP4-CANDU) was developed to assess the consequences of a severe core damage progression in a CANDU nuclear power station. The results from MAAP4-CANDU analyses support Level 2 PSA activities being performed for CANDU stations. During the early stages of a severe core damage accident in a CANDU plant, the primary heat transport system (PHTS) coo...

The effect of variation in thermal conductivity of light water reactor fuel elements on core response during loss-of-coolant accident scenarios is examined. Initially, a simplified numerical analysis is utilized to determine the time scales associated with dissipation of stored energy from the fuel into the coolant once the fission reaction is stopped. The analysis is then followed by full reac...

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 ind...

The Spent Fuel Pool (SFP) in a nuclear power plant is robust structure designed to withstand large seismic loads. After the terrorist attacks on September 11 and accident Fukushima plant, special attention was focused safety assessments taking measures mitigate possible accidents related spent fuel pool. This paper will provide an insight into pool loss of coolant phenomenology consequence miti...