간극에서의 역방향 유동 제한 현상 연구

Counter-Current Flow Limit in Narrow Gap

  • 김용훈 (서울대학교 공과대학 원자핵공학과) ;
  • 서균렬 (서울대학교 공과대학 원자핵공학과)
  • Kim, Yong-Hoon (Department of Nuclear Engineering, Seoul National University) ;
  • Suh, Kune-Y. (Department of Nuclear Engineering, Seoul National University)
  • 발행 : 1998.11.28

초록

Previous counter-current flow limitation (CCFL) and critical heat flux (CHF) studies included investigations on the inlet entrance, inclined channel and gap effects for the most part. In this study, the local CHF correlation was presented to be used in the numerical analysis for the 3 dimensional hemispherical geometry. Also, first-principle analyses were performed to determine the maximum heat removal capability from the debris through the gap that may be formed during a core melt accident. The maximum heat removal capability by gap cooling can be applied in quantitatively assessing the severe accident management measures.

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