主催: The Japan Society of Mechanical Engineers
会議名: 第30回 原子力工学国際会議（ICONE30）
開催日: 2023/05/21 - 2023/05/26
In order to ensure the integrity of the containment in accidents, passive containment heat removal system (PCS) is designed in the new generation of nuclear power plants. This system typically consists of a heat exchanger, pipes and a water tank. In accidents, the water in the heat exchanger could be heated, which result in naturally circulating of the water in the PCS and cooling of the mixture in the containment. In order to obtain the operating characteristics of PCS and analyze the mitigation effect of PCS on accidents, a computational model based on finite volume method and modified staggered grid was developed. The model considered the PCS loop as a one-dimensional flow system, which was solved by discretized one-dimensional conservation equations. The model was planted in CONTHAC-3D, which was a containment thermal-hydraulic analysis program. CONTHAC-3D with new PCS model was validated with steady and oscillation experiment results. Important parameters such as PCS heat exchange power, mass flow rate, in-containment pressure and temperature were compared. The deviations from the experiment results to simulations results of CONTHAC-3D were within ±7.0 %, which indicated CONTHAC-3D with new PCS model could be useful in PCS design and accident analysis.
