광범위한 압력조건하에서 균일 가열 수직 봉다발에서의 임계열유속

Critical Heat Flux in Uniformly Heated Rod Bundle Under Wide Range of System Pressures

  • 문상기 (한국원자력연구소 열수력안전연구팀) ;
  • 천세영 (한국원자력연구소 열수력안전연구팀) ;
  • 최기용 (한국원자력연구소 열수력안전연구팀)
  • 발행 : 2001.06.27

초록

An experimental study on critical heat flux (CHF) has been performed for water flow in a uniformly heated vertical 3 by 3 rod bundle under low flow and a wide range of pressure conditions. The objective of this study is to investigate the parametric trends of CHF with 3 by 3 rod bundle test section where three unheated rods exist. The general trends of the CHF are coincident with previous understandings. At low flow and system pressure above 3 MPa, some critical qualities are larger than 1.0 due to counter-current flow in test sections. Since there is a supply of water to the heated section from unheated section, the maximum CHFs at system pressure between 2 and 4 MPa are not shown.

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