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배관 파단 현상에 따른 연구용 원자로 사이폰 차단 현상 분석
서경우(Kyoung Woo Seo),박홍범(Hong Beom Park),정민규(Min Kyu Jung),박기정(Ki-Jung Park),김성훈(Seong Hoon Kim) 대한기계학회 2017 대한기계학회 춘추학술대회 Vol.2017 No.11
For the research reactor, the primary coolant system (PCS) connected to the reactor is designed to penetrate the pool. During a loss of coolant accident (LOCA), the pool water should be prevented from draining below the top of the reactor for removing the residual heat using the natural circulation in the pool. The siphon breakers are installed to the branch line of the PCS to maintain the pool level during LOCA. In this study, the siphon break phenomena for a LOCA of the research reactor are analyzed by ANSYS-CFD. The calculations are performed according to the characteristic of the broken pipe. When the siphon and main pipe size are 4 and 16 inch respectively, and the height between the pool and the break location is 12.2m, the undershooting height is estimated lower than 0.45m.
윤현기(Hyun Gi Yoon),서경우(Kyoung Woo Seo) 대한기계학회 2017 대한기계학회 춘추학술대회 Vol.2017 No.11
Open pool type research reactor is widely designed and operated in consideration of the reactor utilization and accessibility. Reactor structure assembly is placed at the pool bottom. Fuel assembly is installed on the grid plate inside a reactor structure assembly. Grid plate is the component of the reactor structure assembly. Primary coolant is dumped into the reactor pool and goes to the fuel assembly through the flow guide structure in the downward flow type research reactor. Heat generated from the fuel assembly is removed by the primary coolant. Grid plate also generates the heat while the reactor is in normal operation. This heat shall be removed to avoid the hot temperature region in the grid plate. Generally, cooling line is designed to remove the heat from the grid plate. In this research, flow path of the primary coolant in the reactor pool is designed to remove the heat from the grid plate. Cooling of the grid plate is numerically simulated by the dumped primary coolant.
이선일(Sunil Lee),서경우(Kyoung Woo Seo) 대한기계학회 2018 대한기계학회 논문집. Transactions of the KSME. C, 산업기술과 혁신 Vol.6 No.2
고온 고압조건을 가진 발전용 상업로와는 달리 저온 저압조건에서 작동되는 연구용 원자로는 일반적으로 핵반응이 발생하는 노심이 개방된 수조수에 담겨 있는 개방수조형 방식으로 설계된다. 이 수조수의 냉각 및 정화를 위해 일차냉각계통을 포함한 다양한 유체계통이 필요하다. 특히 일차냉각계통은 정상출력운전 중 노심에서 발생되는 열을 일차냉각계통 펌프와 열교환기를 이용하여 제거하는 역할을 한다. 일차냉각계통 펌프가 정지되면 일차냉각계통 펌프의 관성바퀴에 의한 관성서행 유량을 통해 노심냉각을 유지하고, 안전잔열제거계통 펌프를 정지하면 플랩밸브를 통한 수조수의 자연순환에 의해 노심붕괴열이 제거된다. 본 논문에서는 개방수조형 연구용 원자로의 노심 냉각을 위한 일차냉각계통에 대해서 설계요건, 계통설명, 계통 운전(기동, 출력운전, 원자로 정지), 설계평가, 검사 및 시험의 항목으로 나누어 자세히 기술하였다. Unlike the nuclear power reactor, the research reactor for the multi-purpose neutron application has been designed with the open-pool type reactor the core is submerged in. The research reactor has several fluid systems such as primary cooling system (PCS), secondary cooling system, pool water management system, and hot water layer system. The primary cooling system removes the fission heat from the core in the normal operation. When the PCS pumps are not in operation after the reactor shutdown or trip, PCS removes the core decay heat by natural circulation through the flap valve. In this paper, the design bases, system description, system operation, design evaluation, inspection and testing for the primary cooling system are specified in detail.