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단위-셀 실험과 전산유체해석을 통한 블록형 초고온가스로의 노심우회유량 평가
윤수종(S.J. Yoon),진창용(C.Y. Jin),김민환(M.H. Kim),박군철(G.C. Park) 한국전산유체공학회 2009 한국전산유체공학회지 Vol.14 No.2
An accurate prediction of the bypass flow is of great importance in the VHTR core design concerning the fuel thermal margin. Nevertheless, there has not been much effort in evaluating the amount and the distribution of the core bypass flow. ln order to evaluate the behavior and the distribution of the coolant flow, a unit-cell experiment was carried out. Unit-cell is the regular triangular section which is formed by connecting the centers of three hexagonal blocks. Various conditions such as the inlet mass flow rate, block combinations and the size of bypass gap were examined in the experiment. CFD analysis was carried out to analyze detailed characteristics of the flow distribution. Commercial CFD code FLUENT 6.3 was validated by comparing with the experimental results. In addition, SST model and standard k-ε model were validated. The results of CFD simulation show good agreements with the experimental results. SST model shows better agreement than standard k-ε model. Results showed that block combinations and the size of the bypass gap have an influence on the bypass flow ratio but the inlet mass flow rate does not.
다중블록실험과 전산유체해석을 통한 블록형 초고온가스로의 노심우회유량 평가
윤수종(S.J. Yoon),이정훈(J.H. Lee),김민환(M.H. Kim),박군철(G.C. Park) 한국전산유체공학회 2011 한국전산유체공학회지 Vol.16 No.3
In the block type VHTR core, there are inevitable gaps among core blocks for the installation and refueling of the fuel blocks. These gaps are called bypass gap and the bypass flow is defined as a coolant flows through the bypass gap. Distribution of core bypass flow varies according to the reactor operation since the graphite core blocks are deformed by the fast neutron irradiation and thermal expansion. Furthermore, the cross-flow through an interfacial gap between the stacked blocks causes flow mixing between the coolant holes and bypass gap, so that complicated flow distribution occurs in the core. Since the bypass flow affects core thermal margin and reactor efficiency, accurate prediction and evaluation of the core bypass flow are very important. In ihis regard, experimental and computational studies were carried out to evaluate the core bypass flow distribution. A multi-block experimental apparatus was constructed to measure flow and pressure distribution. Multi-block effect such as cross flow phenomenon was investigated in the experiment. The experimental data were used to validate a CFD model for analysis of bypass flow characteristics in detail.