R&D issues for SiCf/SiC composites structural material in fusion power reactor blankets

被引:31
作者
Giancarli, L [1 ]
Aiello, G
Caso, A
Gasse, A
Le Marois, G
Poitevin, Y
Salavy, JF
Szczepanski, J
机构
[1] CEA Saclay, DRN, DMT, F-91191 Gif Sur Yvette, France
[2] Soc Europeenne Propuls, DPPC, F-33165 St Medard en Jalles, France
[3] CEA Grenoble, DEM, SGM, F-38054 Grenoble, France
关键词
R&D issues; composites; reactor blankets;
D O I
10.1016/S0920-3796(00)00150-2
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
The main features of recent fusion reactor blanket conceptual designs using SiCf/SiC as structural material are presented. Particular attention is paid to the adopted safety and maintenance strategy. Two main blanket lines have been identified, depending on the used coolant, either helium or Pb-17Li. Their main performances are discussed taking into account the assumed material properties in comparison with those of available industrial materials. The main properties of some advanced industrial SiCf/SiC composites are given and the need for further improvement of properties and/or further development for the manufacturing techniques are defined as a function of the particular blanket line. (C) 2000 Elsevier Science S.A. All rights reserved.
引用
收藏
页码:509 / 520
页数:12
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