Paper Title:
Corrosion Experiments of the Candidate Materials for Liquid Lithium Lead Blanket of Fusion Reactor
  Abstract

Liquid lithium lead (LiPb) eutectic is considered as one of the promising candidates of tritium breeder materials for fusion reactors. Series experiments on compatibility of LiPb with candidate structural materials such as CLAM steel and SiC f/SiC composites have been done in DRAGON serious experimental devices in FDS team such as DRAGON-RTand stirred pot device in NIFS at 500 oC and 600oC, respectively. The weight loss of CLAM specimens exposed in flowing LiPb with the velocity of 0.17m/s increased with temperature, and the morphology and composition of the corroded surfaces were done by SEM observation and EDX analysis. The coating specimens including Al 2O3 and FeAl/Al2O3 coatings prepared on the CLAM specimens were also exposed in the DRAGON-RT device, the results revealed that there was no obvious thinning observed on the outer surface of the protective coating. Preliminary analysis of SiC f/SiC composites specimens indicated that the mullite coating with plasma spray method on the SiC f/SiC composites specimen corroded in the high temperature LiPb, but no obvious corrosion attack was observed on the specimen surface, while the matrix and fiber of reaction-sintered composites showed slightly corrosion attack after exposure in static LiPb at 800°C for 200 hrs. Further corrosion experiment will be carried out in the near future.

  Info
Periodical
Edited by
Pietro VINCENZINI, Hua-Tay LIN and Kevin FOX
Pages
41-50
DOI
10.4028/www.scientific.net/AST.73.41
Citation
Q. Y. Huang, S. Gao, Z. Q. Zhu, Z. H. Guo, X. Z. Ling, Z. L. Yan, M. Kondo, V. Tsisar, T. Muroga, Y. C. Wu, "Corrosion Experiments of the Candidate Materials for Liquid Lithium Lead Blanket of Fusion Reactor", Advances in Science and Technology, Vol. 73, pp. 41-50, 2010
Online since
October 2010
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