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ASSESSMENT of CORE BYPASS FLOW IN A PRISMATIC VERY HIGH TEMPERATURE REACTOR BY USING MULTI-BLOCK EXPERIMENT and CFD ANALYSIS

다중블록실험과 전산유체해석을 통한 블록형 초고온가스로의 노심우회유량 평가

  • 윤수종 (서울대학교 대학원 원자핵공학과) ;
  • 이정훈 (서울대학교 대학원 원자핵공학과) ;
  • 김민환 (한국원자력연구원 수소생산원자로기술개발부) ;
  • 박군철 (서울대학교 원자핵공학과)
  • Received : 2011.08.25
  • Accepted : 2011.09.17
  • Published : 2011.09.30

Abstract

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 this 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 foranalysis of bypass flow characteristics in detail.

Keywords

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