Host: The Japan Society of Mechanical Engineers
Name : The 30th International Conference on Nuclear Engineering (ICONE30)
Date : May 21, 2023 - May 26, 2023
Interfacing System Loss of Coolant Accident (ISLOCA) is an important initiating event in nuclear power plants (NPP). After the occurrence of ISLOCA in a NPP, if it is not isolated in time, the reactor coolant will continue to flow out of the containment, and the core will eventually be exposed and damaged. In the internal events Probabilistic Risk Assessment (PRA), the ISLOCA risk has been quantitatively assessed, but only the random failure modes of the equipment have been considered. In case of fire, multiple components are affected simultaneously, and the probability of spurious actuation is greatly increased due to cable short circuits, potentially leading to an increased risk of ISLOCA. Taking the third-generation pressurized water reactor NPP as an example, this paper conducted the method research and risk assessment of fire induced ISLOCA by screening and analyzing the path of the interface system connected to the primary circuit.
