核融合研究
Online ISSN : 1884-9571
Print ISSN : 0451-2375
ISSN-L : 0451-2375
核融合動力炉への先駆的高熱負荷除去技術
戸田 三朗
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ジャーナル フリー

1991 年 65 巻 1 号 p. 5-24

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High heat flux components of a fusion power reactor, first wall, diverter and limiter, are required to be cooled stably and safely at much higher levels of temperature, heat flux and power density than conceptual designs presented previously such as Starfire. However, conventional methods of cooling using single phase flow of pressurized water, helium gas or liquid metal want ability to perform the required function. Further requirements are discussed, and recent studies on advanced cooling techniques using two-phase flow of liquid metal-gas or solid particles-gas are stated.

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