Heat Transfer Characteristics of an Annulus Channel Cooled with R-134a Fluid near the Critical Pressure

임계압력 근처에서의 환형관 채널에 대한 열전달 특성 연구

  • 홍성덕 (한국원자력연구소 열수력안전연구부) ;
  • 천세영 (한국원자력연구소 열수력안전연구부) ;
  • 김세윤 (한국원자력연구소 열수력안전연구부) ;
  • 백원필 (한국원자력연구소 열수력안전연구부)
  • Published : 2004.04.28

Abstract

An experimental study on heat transfer characteristics near the critical pressure has been performed with an internally-heated vertical annular channel cooled by R-134a fluid. Two series of tests have been completed: (a) steady-state critical heat flux (CHF) and (b) heat transfer tests for pressure reduction transients through the critical pressure. In the present experimental range, the steady-state CHF decreases with the increase of the system pressure For a fixed inlet mass flux and subcooling, the CHF falls sharply at about 3.8 MPa and shows a trend toward converging to zero as the pressure approaches the critical point of 4.059 MPa. The CHF phenomenon near the critical pressure does not lead to an abrupt temperature rise of the heated wall because the CHF occurred at remarkably low power levels. In the pressure reduction transient experiments, as soon as the pressure passed through the critical pressure, the wall temperatures rise rapidly up to a very high value due to the occurrence of the departure from nucleate boiling. The wall temperature reaches a maximum at the saturation point of the outlet temperature, then tends to decrease gradually.

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