Progress in compatibility experiments on lithium-lead with candidate structural materials for fusion in China

被引:66
作者
Huang, Qunying [1 ,2 ]
Gao, Sheng [1 ,2 ]
Zhu, Zhiqiang [1 ,2 ]
Zhang, Maolian [1 ,2 ]
Song, Yong [1 ,2 ]
Li, Chunjing [1 ,2 ]
Chen, Yaping [1 ,2 ]
Ling, Xinzhen [1 ,2 ]
Zhou, Xingui [3 ]
机构
[1] Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China
[2] Univ Sci & Technol China, Sch Nucl Sci & Technol, Hefei 230027, Anhui, Peoples R China
[3] Natl Univ Def Technol, Coll Aerosp & Mat Engn, Changsha 410073, Hunan, Peoples R China
基金
中国国家自然科学基金;
关键词
Lithium lead; Structural materials; CLAM steel; Compatibility; TEST BLANKET MODULE; CORROSION BEHAVIOR; CONCEPTUAL DESIGN; PB-17LI; STRATEGY; STEEL; ITER;
D O I
10.1016/j.fusengdes.2008.12.038
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
Liquid LiPb eutectic is one of the promising candidate tritium breeder materials for fusion reactors. This paper presents the progress in compatibility experiments with liquid LiPb achieved up to now in China for some candidate structural materials. The results showed that CLAM steel had good compatibility with flowing LiPb at 480 degrees C with the velocity of 0.08 m/s after 5000 h in DRAGON-I loop. On the other hand, after exposed in static LiPb at 700 degrees C for 500 h in a SiC crucible, the W and Mo specimens suffered much more weight loss compared with Nb specimen, and a thin reaction product layer was visible on the surface of all the three refractory metals. Preliminary analysis on SiC(f)/SiC composite specimens indicated that there was no penetration of LiPb and no reaction products on the surface with CVD SiC coating, which showed SiCf/SiC composite were stable and compatible with static LiPb under 700 degrees C after 500h exposure. (C) 2008 Elsevier B.V. All rights reserved.
引用
收藏
页码:242 / 246
页数:5
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