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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D O I：

暂无

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.

引用

页码：1173 / 1178

页数：6

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