ITER - DESIGN OVERVIEW

被引：0
|
作者：
TOMABECHI, K
机构：
来源：
JOURNAL OF NUCLEAR MATERIALS | 1991年 / 179卷
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中图分类号：
T [工业技术];
学科分类号：
08 ;
摘要：
The ITER design, jointly conducted by Euratom, Japan, USSR and USA under the auspices of the IAEA, is progressing with an optimized tokamak machine, having a major radius of 6.0 m, magnetic field on axis of 4.85 T, and a nominal plasma current of 22 MA. This paper describes major parameters of the machine as well as the design of the superconducting magnets, first wall, divertor and blanket/shield which are particularly relevant to fusion reactor materials research and development.
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页码：1173 / 1178
页数：6
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