Candidate blanket concepts for a European fusion power plant study

被引：31

作者：

Giancarli, L ^{[1
]}

Ferrari, M

Fütterer, MA

Malang, S

机构：

[1] CEA Saclay, DRN, DMT, F-91191 Gif Sur Yvette, France

[2] ENEA, CR Frascati, I-00044 Frascati, Rome, Italy

[3] Forschungszentrum Karlsruhe, D-76021 Karlsruhe, Germany

来源：

FUSION ENGINEERING AND DESIGN | 2000年 / 49-50卷

关键词：

blanket concept; fusion power plant; Europe;

D O I：

10.1016/S0920-3796(00)00278-7

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 breeding blanket is an essential in-vessel component for fusion power plants based on the deuterium-tritium fuel. It is submitted to severe operating conditions such as high surface heat flux on the first wall (> 0.5 MW/m(2)) and to very high 14 MeV neutron flux (>10(18) n/m(2) s). Because of the simultaneous requirement of very demanding performances, such as tritium breeding self-sufficiency, high thermal cycle efficiency, high availability and high safety standards, the number of candidate breeding blanket concepts is limited. After recalling advantages and drawbacks of possible combinations of structural materials, coolants, and breeder materials, this paper summarizes the characteristics and the performances of some potential candidate concepts for a European power plant study and associated required R&D. (C) 2000 Elsevier Science B.V. All rights reserved.

引用

页码：445 / 456

页数：12

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