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KMID : 0371819970290040348
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Nuclear Engineering and Technology
1997 Volume.29 No. 4 p.348 ~ p.359
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Coolant Options and Critical Heat Flux Issues in Fusion Reactor Divertor Design
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Baek Won-Pil
Chang Soon-Heung
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Abstract
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This paper reviews cooling aspects of the divertor system in Tokamak fusion devices with primary emphasis on the critical heat flux (CHF) issues for vster-cooled designs. General characteristics of four (4) coolant options for divertor cooling gases, water, liquid metal, and organic liquid are discussed first, focusing on the comparison of advantages and disadvantages of those options. Then results of recent studies on the high-heat-flux CHF of water at subcooled high-velocity conditions are reviewed to provide a general idea on the feasibility of the venter-cooled divertor concept for fu. ture Tokamak fusion reactors. Water is assessed to be the most viable and practical coolant option for divertors of future experimental Tokamaks.
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KEYWORD
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