Fissile core and Tritium-Breeding Blanket: structural materials and their requirements

被引:70
作者
Boutard, Jean-Louis [1 ]
Alamo, Ana [2 ]
Lindau, Rainer [3 ]
Rieth, Michael [3 ]
机构
[1] EFDA CSU Garching, D-85748 Garching, Germany
[2] CEA Saclay, DEN DSOE, F-91191 Gif Sur Yvette, France
[3] IMF FZK 1, D-76344 Eggenstein Leopoldshafen, Germany
关键词
structural materials; ferritic/martensitic steels; ferritic steels; SiCf/SiC composites; radiation effects;
D O I
10.1016/j.crhy.2007.11.004
中图分类号
P1 [天文学];
学科分类号
0704 ;
摘要
High radiation resistant structural materials for fusion and fission nuclear power plants are a key issue for the development of both types of reactors. Selection criteria, elements of metallurgy of the selected materials, and the major issues as they are revealed by the results of the present development programmes, are presented. At low temperature (similar to 300 degrees C) ferritic/martensitic steels are suffering from He-embrittlement, associated with possible hardening due to alpha/alpha' unmixing. The kinetics of hardening and embrittlement versus dose, especially saturation with dose, are still open key issues, difficult to settle on the basis of a purely experimental programme. Important progress is still to be made in mastering the initial microstructure, inclusion cleanness and joining techniques of oxide dispersion strengthened steels for higher heat resistance. Physics modeling as presented in this issue should promote guidance to the understanding of the mechanisms involved, provide solutions to master the initial microstructure and phase stability, and mitigate the in-service property degradation.
引用
收藏
页码:287 / 302
页数:16
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