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개방수조형 연구용 원자로 유체계통에서 밸브 슬램에 의한 수충격 방지 설계
김다용(Dayong Kim),박홍범(Hong-Beom Park) 대한기계학회 2022 대한기계학회 춘추학술대회 Vol.2022 No.11
Unlike the nuclear power reactor, the research reactor operates under low temperature and low pressure condition, and are designed for an open pool type with the cored immersed in open pool. Thus, the water hammer phenomenon that can occur in the fluid system are different due to the different design characteristics of two reactors. Therefore, this study is presented the design for water hammer prevention by valve slam, which shall be considered in the design of research reactor among the causes of water hammer in nuclear power reactor. Water hammer by valve slam is caused by rapid valve closure due to failure of valve actuator or dynamic behavior of check valve due to reversed velocity by pump trip. The water hammer by rapid vale closure is prevented by design the length of the piping in the fluid system as short as possible. The water hammer by dynamic behavior of check valve is prevented by installation the fast response check valve such as tilted disc check valve in fluid system.
개방수조형 연구용 원자로 유체계통에서 밸브 슬램에 의한 수충격 방지 설계
김다용(Dayong Kim),박홍범(Hong-Beom Park) 대한기계학회 2022 대한기계학회 춘추학술대회 Vol.2022 No.11
Unlike the nuclear power reactor, the research reactor operates under low temperature and low pressure condition, and are designed for an open pool type with the cored immersed in open pool. Thus, the water hammer phenomenon that can occur in the fluid system are different due to the different design characteristics of two reactors. Therefore, this study is presented the design for water hammer prevention by valve slam, which shall be considered in the design of research reactor among the causes of water hammer in nuclear power reactor. Water hammer by valve slam is caused by rapid valve closure due to failure of valve actuator or dynamic behavior of check valve due to reversed velocity by pump trip. The water hammer by rapid vale closure is prevented by design the length of the piping in the fluid system as short as possible. The water hammer by dynamic behavior of check valve is prevented by installation the fast response check valve such as tilted disc check valve in fluid system.
연구용 원자로의 원자로 구조물 집합체 스트레이너에서의 압력강하 평가
윤현기(Hyungi Yoon),김다용(Dayong Kim),서재광(Jae-kwang Seo) 대한기계학회 2018 대한기계학회 춘추학술대회 Vol.2018 No.12
Open pool type research reactor is widely designed in consideration of the reactor utilization and accessibility. A coolant flows into a reactor structure assembly and goes to fuel assemblies in the downward flow type reactor. Inlet and outlet pipes of the primary coolant system are directly connected to the reactor structure assembly. The primary coolant system circulates the coolant from the reactor core to the heat exchanger in order to remove the fission heat continuously. There are holes in the reactor structure assembly for the by-pass flow path and the reactor utilization. The strainer is installed on each hole to prevent to enter foreign materials from the reactor pool to fuel assemblies. When the loss of coolant accident occurs in the pipe of the primary coolant system, the coolant is flowed out from the reactor pool to the primary coolant system through strainers. The loss coefficient of the strainer is one factor to determine the flow rate. The flow field of the strainer is numerically simulated to calculate the loss coefficient based on the velocity and pressure. The loss coefficient of 8.0 ± 1.0 is obtained from the numerical and analytical methods.