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박용철(Y.C. Park),지대영(D.Y. Chi),서경우(K.W. Seo),윤현기(H.G. Yoon),박정근(J.G. Park) 한국전산유체공학회 2011 한국전산유체공학회 학술대회논문집 Vol.2011 No.5
During a reactor normal operation, a primary coolant was designed to remove the fission reaction heat of the reactor. When one pump is failure and the other pump shall supply the cooling water to cool the reduced power, it is necessary to estimate how much flow will be supplied to cool the reactor. We carried a flow net work analysis for two parallel pumping system as based on the piping net work of the primary cooling system in HANARO. As result, it is estimated thai the flow of one pump increased than the rated flow of the pump below the cavitation critical flow.
박용철(Y.C. Park),윤현기(H.G. Yoon),서경우(K.W. Seo),지대영(D.Y. Chi),윤주현(J.H. Yoon) 한국전산유체공학회 2012 한국전산유체공학회 학술대회논문집 Vol.2012 No.5
In nuclear power plant, the reactor cooling system has maintained high-Reynolds-number flow above 1E+07 to cool a heat generated by the reactor. To minimize uncertainty for flow calibration, it is necessary to install a flow simulation system to maintain the high-Reynolds-number flow. Y-connection is selected to connect four (4) parallel high flow circulation pumps for minimizing system pressure loss. This paper describes the characteristics for Y-connection by computer flow simulation. It was confirmed through the results that the pressure loss of the Y-connection was lower than that of T-connection, and that the pressure loss of the connection was similar sixty degree (60°) and below of connection angle.
연구용 원자로 수조고온층계통에서의 입구 및 출구 배관 설계
윤현기(H.G. Yoon),서경우(K.W. Seo),박용철(Y.C. Park),지대영(D.Y. Chi) 한국전산유체공학회 2012 한국전산유체공학회 학술대회논문집 Vol.2012 No.5
The Hot Water Layer System(HWLS) maintains the hot water layer, higher than the average temperature of the pool water, at the upper part of the reactor and service pools so as to minimize the radioactive primary coolant rising up to the pool surface by natural convection in the open pool type research reactor. The ends of the suction and discharge lines ore submerged below the pool surface and located at the same level in the reactor pool. The end shape of the discharge pipe is designed as a T-shape diffuser to distribute the flow uniformly for stable hot water layer formation at the upper section of the reactor and service pools. Heat loss, temperature stratification and velocity boundary layer are taken into consideration to determine the formation of the stable hot water layer through the numerical simulation. Commercial code FLUENT is used to calculate the unsteady pool water flow with different T-shape diffusers and locations of the suction pipe. Also, two kinds of turbulent model, RNG k-e and SST k-w turbulent model, are used for the conservative system design.
연구로의 PCS discharge header 설계를 위한 CFD 해석
서경우(K.W. Seo),윤현기(H.G. Yoon),지대영(D.Y. Chi),윤주현(J.H. Yoon) 한국전산유체공학회 2012 한국전산유체공학회 학술대회논문집 Vol.2012 No.5
The heat generated from the core of a research reactor is removed by a primary cooling system (PCS). Most reactors of relatively low power are designed using an open type reactor and pool. Thus, the primary coolant can be discharged to the reactor pool. However, the discharged coolant toward the top of the open type pool should be minimized for operator safety because it contains many kinds of radio-nuclides. This means that it is important for a PCS discharge header to be designed for minimizing bulk flow in the pool. ANSYS-CFD was employed to design a PCS discharge header and to analyze the flow characteristics in the pool. Several discharge headers were simulated with a similar scaled geometry and the boundary conditions of an actual research reactor. To minimize the bulk flow toward the top of the pool, it was analyzed that the magnitude and direction of velocity at the hole of the discharge header should be reduced. The results showed that the CFD analysis can be used as a tool for designing and modifying the PCS discharge according to various types of reactor pools.
개방형 수조 형태의 연구용 원자로 수조고온층계통에서의 T-형태 유동 분출 배관 설계
윤현기(H.G. Yoon),서경우(K.W. Seo),김성훈(S.H. Kim),지대영(D.Y. Chi) 한국전산유체공학회 2013 한국전산유체공학회 학술대회논문집 Vol.2013 No.5
The Hot Water Layer System(HWLS) maintains the hot water layer, higher than the average temperature of the pool water, at the upper part of the reactor pool so as to minimize the radioactive primary coolant rising up to the pool surface by natural convection in the open pool type research reactor. The ends of the suction and discharge lines of the HWLS are submerged below the pool surface and located at the same level in the reactor pool. The end shape of the discharge pipe is designed as a T-shape diffuser to distribute the flow uniformly for stable hot water layer formation at the upper section of the reactor and service pools. On the other hand, the commercial pipe is used as the end suction line. This pipe line is just extruded into the pool with a short length. In this research, flow fields of the reactor and service pools are numerically simulated with different sizes of the pipes. Heat loss, temperature stratification and velocity boundary layer are taken into consideration to determine the formation of the stable hot water layer through the numerical simulation. Commercial code FLUENT is used to calculate the unsteady pool water flow with different T-shape diffusers and locations of the suction pipe. Inlet and outlet pipe sizes of the HWLS are decided based on the simulation results.
서경우(K.W. Seo),윤현기(H.G. Yoon),김성훈(S.H. Kim),지대영(D.Y. Chi),윤주현(J.H. Yoon) 한국전산유체공학회 2013 한국전산유체공학회 학술대회논문집 Vol.2013 No.5
In a research reactor, the large pool water is at the heart of safety because a thermal design flow during a normal operation or a flow path for a natural circulation during an abnormal reactor trip shall be supplied for core cooling. Most research reactors include a reactor in the enormous pool, and are designed using an open type reactor and pool. Thus, the primary coolant containing many kinds of radio-nuclides can be mixed to the reactor pool. Because operators can operate near the pool top during a normal operation, the bulk flow toward the top of the open type pool should be designed to be minimized.
연구용 원자로의 decay tank 내부 구조물 설계를 위한 해석
서경우(K. W. Seo),박홍범(H. B. Park),윤현기(H .G. Yoon),김성훈(S. H. Kim),지대영(D. Y. Chi) 한국전산유체공학회 2014 한국전산유체공학회 학술대회논문집 Vol.2014 No.5
The primary coolant after passing through the reactor core contains many kinds of radio-nuclides, especially N-16 for a research reactor. The decay tank including internal structures is designed to provide enough transit time to ensure that the N-16 activity decreases before the coolant leaves the decay tank’s shielding room. To design the decay tank, the flow and pressure distributions were calculated using the commercially available CFD code, ANSYS-CFD. The cell modeling was performed to supply the conservative input for the stress analysis. The CFD results showed that the stress was concentrated near the center of the first perforated plate by the flow induced from the inlet. The pressure loss between the inlet and outlet of the decay tank will be used for the design of the pump and the primary cooling system.