Journal of computational fluids engineering (한국전산유체공학회지)

Korean Society of Computational Fluids Engineering (한국전산유체공학회)
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ASSESSMENT OF CORE BYPASS FLOW IN A PRISMATIC VERY HIGH TEMPERATURE REACTOR BY USING UNIT-CELL EXPERIMENT AND CFD ANALYSIS

단위-셀 실험과 전산유체해석을 통한 블록형 초고온가스로의 노심우회유량 평가

  • 윤수종 (서울대학교 대학원 원자핵공학과) ;
  • 진창용 (서울대학교 대학원 원자핵공학과) ;
  • 김민환 (한국원자력연구원 수소생산원자로기술개발부) ;
  • 박군철 (서울대학교 원자핵공학과)
  • Published : 2009.06.30
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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.

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