Selection, development and characterisation of plasma facing materials for ITER

被引：52

作者：

Barabash, V

Akiba, M

Mazul, I

Ulrickson, M

Vieider, G

机构：

[1] JAPAN ATOM ENERGY RES INST, NAKA, IBARAKI 31101, JAPAN

[2] DV EFREMOV INST ELECTROPHYS APPARATUS, ST PETERSBURG 189631, RUSSIA

[3] SANDIA NATL LABS, ALBUQUERQUE, NM 87185 USA

[4] NET TEAM, D-85748 GARCHING, GERMANY

来源：

JOURNAL OF NUCLEAR MATERIALS | 1996年 / 233卷

关键词：

D O I：

10.1016/S0022-3115(96)00323-6

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

The current status of the selection of the armour materials for first wall, limiters and divertor are presented. The candidate armour materials are beryllium, tungsten and carbon base materials (mainly carbon fiber composites), The selection of the references grades from these material classes is discussed and the candidate grades are described, The main reasons for the selection of the reference grades are also discussed, The urgent materials R&D needs for the development of the design are described briefly.

引用

页码：718 / 723

页数：6

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