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ASSESSMENT OF CORE BYPASS FLOW IN A PRISMATIC VERY HIGH TEMPERATURE REACTOR BY USING UNIT-CELL EXPERIMENT AND CFD ANALYSIS  

Yoon, S.J. (서울대학교 대학원 원자핵공학과)
Jin, C.Y. (서울대학교 대학원 원자핵공학과)
Kim, M.H. (한국원자력연구원 수소생산원자로기술개발부)
Park, G.C. (서울대학교 원자핵공학과)
Publication Information
Journal of computational fluids engineering / v.14, no.2, 2009 , pp. 59-67 More about this Journal
Abstract
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. In 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-$\varepsilon$ model were validated. The results of CFD simulation show good agreements with the experimental results. SST model shows better agreement than standard k-$\varepsilon$ 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.
Keywords
Very High Temperature Reactor; Block-type Core; Graphite Block; Core Bypass Flow; Bypass Gap; Unit-Cell; CFD;
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  • Reference
1 1996, General Atomics, "GT-MHR Conceptual Design Description Report 910720," GA Report, General Atomics
2 1994, Burchell, T.D. et al., "The Effect of Neutron Irradiation on the Structure and Properties of Carbon-Carbon Composite Materials," Journal of Nuclear Materials, vol. 191-194, pp.295-299   DOI   ScienceOn
3 1993, Menter, F.R. "Zonal Two Equation k-w Turbulence Models For Aerodynamic Flow," AIAA 93-2906
4 1997, Bardina, J.E. et al., "Turbulence Modeling Validation," AIAA 97-2121
5 2006, Fluent Inc., FLUENT 6.3 User's Guide, Fluent Inc., Lebanon, NH
6 2005, MacDonald, P.E., "Next Generation Nuclear Plant Research and Development Program Plan," INEEL/EXT-05- 02581, INL
7 2005, 백원필 외9인, "평균 양방향 유동 튜브 개념을 이용한 국산 고유 유량계 개발," KAERI/RR-2621, 한국원자력연구원
8 2004, Independent Technology Review Group, "Design Features and Technology Uncertainties for the Next Generation Nuclear Plant," INEEL/EXT-04-01816, INL
9 2006, Vilim, R.B. et al., "Prioritization of VHTR System Modeling Needs Based on Phenomena Identification, Ranking and Sensitivity Studies," ANL-GenIV-071, ANL
10 2004, Fluent Inc., GAMBIT 2.2 User's Guide, Fluent Inc., Lebanon, NH