Carbon fiber composites application in ITER plasma facing components

被引：28

作者：

Barabash, V

Akiba, M

Bonal, JP

Federici, G

Matera, R

Nakamura, K

Pacher, HD

Rodig, M

Vieider, G

Wu, CH

机构：

[1] ITER Joint Cent Team, D-85748 Garching, Germany

[2] Japan Atom Energy Res Inst, Naka, Ibaraki 31101, Japan

[3] CENS, Lab Etud Mat Absorbants, F-91191 Gif Sur Yvette, France

[4] Net Team, D-85748 Garching, Germany

[5] Forschungszentrum Julich, Assoc EURATOM KFA, D-52425 Julich, Germany

来源：

JOURNAL OF NUCLEAR MATERIALS | 1998年 / 258卷

关键词：

D O I：

10.1016/S0022-3115(98)00267-0

中图分类号：

T [工业技术];

学科分类号：

08 ;

摘要：

Carbon Fiber Composites (CFCs) are one of the candidate armour materials for the plasma facing components of the International Thermonuclear Experimental Reactor (ITER). For the present reference design, CFC has been selected as armour for the divertor target near the plasma strike point mainly because of unique resistance to high normal and off-normal heat loads. It does not melt under disruptions and might have higher erosion lifetime in comparison with other possible armour materials. Issues related to CFC application in ITER are described in this paper. They include erosion lifetime, tritium codeposition with eroded material and possible methods for the removal of the codeposited layers, neutron irradiation effect, development of joining technologies with heat sink materials, and thermomechanical performance. The status of the development of new advanced CFCs for ITER application is also described. Finally, the remaining R&D needs are critically discussed. (C) 1998 Elsevier Science B.V. All rights reserved.

引用

页码：149 / 159

页数：11

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