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Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures 0.57 to 15.0 MPa
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  • Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures 0.57 to 15.0 MPa
  • Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures 0.57 to 15.0 MPa
저자명
Chun. Se-Young,Chung. Heung-June,Hong. Sung-Deok,Yang. Sun-Kyu,Chung. Moon-Ki
간행물명
Journal of the Korean Nuclear Society
권/호정보
2000년|32권 2호|pp.128-141 (14 pages)
발행정보
한국원자력학회
파일정보
정기간행물|ENG|
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이 논문은 한국과학기술정보연구원과 논문 연계를 통해 무료로 제공되는 원문입니다.
서지반출

기타언어초록

The critical heat flux (CHF)experiments have been carried out in a wide range of pressures for an internally heated vertical annulus. The experimental conditions covered ranges of pressures from 0.57 to 15.01 MPa, mass fluxes of 0 kg/$m^2$s and from 200 to 650 kg/$m^2$s, and inlet subcoolings from 85 to 413 kJ/kg. The characteristics of the present data and the effect of pressure on CHF are discussed. Most of the CHFs were identified to dryout of the liquid film in the annular or annular-mist flow. For the mass flux of 200 kg/$m^2$s, there were the indications that the CHF occurred at the transition from annular to annular-mist How in the pressure range of 3~10 MPa. For the mass fluxes of 550 and 650 kg/$m^2$s, the CHFs had a maximum value at a pressure of 2~3 MPa, and the pressure at the maximum CHF values had a trend moving toward the pressure at the peak value of pool boiling CHF as the mass flux decreased. The CHF data under a zero mass flux condition indicate that both the effects of pressure and inlet subcooling on the CHF were smaller, compared with those on the CHF with net water upward flow.