Article ID | Journal | Published Year | Pages | File Type |
---|---|---|---|---|
10293416 | Nuclear Engineering and Design | 2005 | 14 Pages |
Abstract
KAERI has performed an experimental study on the critical heat flux (CHF) under zero flow conditions with a non-uniformly heated 3Â ÃÂ 3 rod bundle. Experimental conditions are in the range of a system pressure from 0.50 to 14.96Â MPa and inlet water subcooling enthalpies from 68 to 352Â kJ/kg. The test section used in the present experiments consisted of a vertical flow channel, upper and lower plenums, and a non-uniformly heated 3Â ÃÂ 3 rod bundle. The experimental results show that the CHFs in low-pressure conditions are somewhat scattered within a narrow range. As the system pressure increases, however, the CHFs show a good parametric trend. The CHFs occur in the upper region of the heated section, but the locations of the detected CHFs move gradually in a downward direction with the increase of the system pressure. Even though the effects of the inlet water subcooling enthalpies and system pressure of the flooding CHF are relatively smaller than those of the flow boiling CHF, the CHF increases by increasing the inlet water subcooling enthalpies. Several existing correlations for the countercurrent flooding CHF based on Wallis's flooding correlation and Kutateladze's criterion for the onset of flooding are compared with the CHF data obtained in the present experiments to examine the applicability of the correlations.
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Authors
Seok Cho, Se-Young Chun, Sang-Ki Moon, Won-Pil Baek, Yoo Kim,