E114 CRITICAL HEAT FLUX IN A UNIFORMLY HEATED VERTICAL ANNULUS AT ZERO INLET FLOW UNDER VARIOUS PRESSURES(Critical heat flux)
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概要
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The experimental study of water CHF (critical heat flux) under zero flow conditions has been carried out in an annulus flow channel with a uniformly heated section over a pressure range of 0.52 to 14.97 MPa. In the present boiling system, the CHFs occur in the upper region of the heated section, in contrast to the results in the experiments for boiling tubes conducted by several investigators. The general trend of the CHF with pressure is that the CHF increases up to a medium pressure of about 6 to 8 MPa and decreases as the pressure is further increased. The present data are compared with the existing flooding CHF correlations. When the correction term with the density ratio proposed in the present work is used with the CHF correlation based on the Wallis flooding correlation, it predicts the measured flooding CHF within the RMS error of 7.0 %.
- 社団法人日本機械学会の論文
- 2000-10-01
著者
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Chun Se-young
Korea Atomic Energy Research Institute
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HONG Sung-Deok
Korea Atomic Energy Research Institute
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Moon Sang-Ki
Korea Atomic Energy Research Institute
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Yang Sun-Kyu
Korea Atomic Energy Research Institute
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Chung Moon-Ki
Korea Atomic Energy Research Institute
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