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KMID : 0371820020340040269
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Nuclear Engineering and Technology
2002 Volume.34 No. 4 p.269 ~ p.285
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An Experimental Study on Heat Transfer Characteristics Just Before Critical Heat Flux in Uniformly Heated Vertical Annulus Under a Wide Range of Pressures
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Chun, Se-Young
Moon, Sang-Ki/Chung, Heung-June/Chung, Moon-Ki/Masanori Aritomi
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Abstract
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heat transfer coefficient;saturated two-phase flow;critical heat flux;high pressure range;modified Chen correlation
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KEYWORD
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