Development of plasma facing components for ITER at Efremov Institute

被引：0

作者：

Belyakov, VA ^{[1
]}

Filatov, OG ^{[1
]}

Mazul, IV ^{[1
]}

机构：

[1] DV Efremov Sci & Res Inst Electrophys Apparatus, St Petersburg 189631, Russia

来源：

17TH IEEE/NPSS SYMPOSIUM ON FUSION ENGINEERING, VOLS 1 AND 2 | 1998年

关键词：

D O I：

暂无

中图分类号：

TM [电工技术]; TN [电子技术、通信技术];

学科分类号：

0808 ; 0809 ;

摘要：

Review of the design and R&D activity related to ITER divertor components development performed in Russia during recent years is presented. The scope of the design work and the codes used in this analysis are briefly reviewed. Among a variety of R&D works the key issues are presented: selection and study of armour materials, development of joining technology and mock-ups manufacturing, high heat nux tests of materials and components. The experimental and technological facilities used for this work are reviewed and a number of the alternative design solutions and experimental approaches are briefly discussed as well.

引用

页码：393 / 396

页数：4