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EXPERIMENTAL INVESTIGATIONS ON HEAT TRANSFER TO CO2 FLOWING UPWARD IN A NARROW ANNULUS AT SUPERCRITICAL PRESSURES
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  • EXPERIMENTAL INVESTIGATIONS ON HEAT TRANSFER TO CO2 FLOWING UPWARD IN A NARROW ANNULUS AT SUPERCRITICAL PRESSURES
  • EXPERIMENTAL INVESTIGATIONS ON HEAT TRANSFER TO CO2 FLOWING UPWARD IN A NARROW ANNULUS AT SUPERCRITICAL PRESSURES
저자명
Kim. Hwan-Yeol,Kim. Hyung-Rae,Kang. Deog-Ji,Song. Jin-Ho,Bae. Yoon-Yeong
간행물명
Nuclear engineering and technology : an international journal of the Korean Nuclear Society
권/호정보
2008년|40권 2호|pp.155-162 (8 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
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기타언어초록

Heat transfer experiments in an annulus passage were performed using SPHINX(Supercritical Pressure Heat Transfer Investigation for NeXt Generation), which was constructed at KAERI(Korea Atomic Energy Research Institute), to investigate the heat transfer behaviors of supercritical $CO_{2}$. $CO_{2}$ was selected as the working fluid to utilize its low critical pressure and temperature when compared with water. The mass flux was in the range of 400 to 1200 $kg/m^{2}s$ and the heat flux was chosen at rates up to 150 $kW/m^{2}$. The selected pressures were 7.75 and 8.12 MPa. At lower mass fluxes, heat transfer deterioration occurs if the heat flux increases beyond a certain value. Comparison with the tube test results showed that the degree of heat transfer deterioration in the heat flux was smaller than that in the tube. In addition, the Nusselt number correlation for a normal heat transfer mode is presented.