DEVELOPMENT OF REDUCED-ACTIVATION MARTENSITIC 9CR STEELS FOR FUSION-REACTOR

被引:31
作者
ABE, F
NODA, T
ARAKI, H
OKADA, M
机构
关键词
FUSION REACTORS; REDUCED ACTIVATION; FERRITIC-MARTENSITIC STEELS; 9CR STEELS; MICROSTRUCTURAL EVOLUTION; TOUGHNESS; HIGH-TEMPERATURE; STRENGTH; CREEP; IRRADIATION HARDENING; TUNGSTEN ADDITIONS; VANADIUM ADDITIONS; CHROMIUM ADDITIONS;
D O I
10.3327/jnst.31.279
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
In order to develop reduced-activation ferritic/martensitic steels potentially suitable for fusion reactor applications, the effect of principal alloying elements Cr, W and V on the microstructural evolution, toughness and high-temperature creep strength was systematically investigated for relatively simple Cr-W-V steels. Based on the results on the simple steels, two kinds of martensitic 9Cr steels with low and high levels of W were alloy-designed: 9Cr-1WVTa and 9Cr-3WVTa. They exhibited excellent toughness and high-temperature strength. Irradiation hardening was the smaller for the reduced-activation 9Cr-1WVTa and 9Cr-3WVTa steels than for the conventional 9Cr-1MoVNb and it was smaller for the low W steel than for the high W steel. It is concluded that from the aspect of toughness the 9Cr-1WVTa steel is the most promising alloy for the first wall and blanket structures which will be operated at low temperatures below 773 K (500-degrees-C). Another 9Cr-3WVTa steel is the most promising in terms of high-temperature creep strength for the future power reactor structures which will be operated at temperatures higher than 773 K.
引用
收藏
页码:279 / 292
页数:14
相关论文
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