International strategy for fusion materials development

被引:85
作者
Ehrlich, K
Bloom, EE
Kondo, T
机构
[1] Forschungszentrum Karlsruhe, Inst Mat Forsch 1, D-76021 Karlsruhe, Germany
[2] Oak Ridge Natl Lab, Div Met & Ceram, Oak Ridge, TN USA
关键词
D O I
10.1016/S0022-3115(00)00102-1
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
In this paper, the results of an IEA-Workshop on Strategy and Planning of Fusion Materials Research and Development (R&D), held in October 1998 in Rise Denmark are summarised and further developed. Essential performance targets for materials to be used in first wall/breeding blanket components have been defined for the major materials groups under discussion: ferritic-martensitic steels, vanadium alloys and ceramic composites of the SiC/SiC-type. R&D strategies are proposed for their further development and qualification as reactor-relevant materials. The important role of existing irradiation facilities (mainly fission reactors) for materials testing within the next decade is described, and the limits for the transfer of results from such simulation experiments to fusion-relevant conditions are addressed. The importance of a fusion-relevant high-intensity neutron source for the development of structural as well as breeding and special purpose materials is elaborated and the reasons for the selection of an accelerator-driven D-Li-neutron source - the International Fusion Materials Irradiation Facility (IFMIF) - as an appropriate test bed are explained. Finally the necessity to execute the materials programme for fusion in close international collaboration, presently promoted by the International Energy Agency, IEA is emphasised. (C) 2000 Elsevier Science B.V. All rights reserved.
引用
收藏
页码:79 / 88
页数:10
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