The development of structural materials for fusion reactors

被引:96
作者
Ehrlich, K [1 ]
机构
[1] Forschungszentrum Karlsruhe, Inst Mat Forsch 1, D-76021 Karlsruhe, Germany
来源
PHILOSOPHICAL TRANSACTIONS OF THE ROYAL SOCIETY A-MATHEMATICAL PHYSICAL AND ENGINEERING SCIENCES | 1999年 / 357卷 / 1752期
关键词
structural materials; radiation-damage parameters; fusion reactor; low-activation materials; intense neutron source; steels; vanadium alloys; ceramic composites;
D O I
10.1098/rsta.1999.0343
中图分类号
O [数理科学和化学]; P [天文学、地球科学]; Q [生物科学]; N [自然科学总论];
学科分类号
07 ; 0710 ; 09 ;
摘要
Structural materials for first-wall and breeding-blanket components will be exposed to 14 MeV neutrons, plasma particles and electromagnetic radiation. In magnetically confined systems, the operation mode will be quasi-continuous. Typical operation conditions for next-step devices and demonstration plants will be described. The selection of suitable structural materials is based on conventional properties, their resistance to radiation-induced damage phenomena and the additional requirement of low neutron-induced radioactivity. Presently, low-activating ferritic-martensitic steels, vanadium alloys and ceramic composites are investigated as promising candidates. In the paper the present status of knowledge is reviewed and the critical issues for the different alternatives are elaborated. The necessity of an appropriate neutron source for the testing and qualification of the materials under fusion-specific conditions is also stressed.
引用
收藏
页码:595 / 617
页数:23
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