SiC coating: An alternative for the protection of nuclear graphite from liquid fluoride salt

SiC coating is produced on a nuclear graphite (NG) substrate using chemical vapor deposition at 1150°C to protect it from molten salt diffusion. Infiltration studies, performed in molten FLiNaK salt under an argon atmosphere at 5atm, show that uncoated NG exhibits significantly higher weight gain th...

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Bibliographic Details
Published in:Journal of nuclear materials 2014-05, Vol.448 (1-3), p.1-3
Main Authors: He, Xiujie, Song, Jinliang, Tan, Jie, Zhang, Baoliang, Xia, Huihao, He, Zhoutong, Zhou, Xingtai, Zhao, Mingwen, Liu, Xiangdong, Xu, Li, Bai, Shuo
Format: Article
Language:English
Subjects:
Applied sciences
Chemical vapor deposition
Coating
Energy
Energy. Thermal use of fuels
Exact sciences and technology
Fission nuclear power plants
Fluorescence
Fluorides
Graphite
Infiltration
Installations for energy generation and conversion: thermal and electrical energy
Liquids
Silicon carbide
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Summary:SiC coating is produced on a nuclear graphite (NG) substrate using chemical vapor deposition at 1150°C to protect it from molten salt diffusion. Infiltration studies, performed in molten FLiNaK salt under an argon atmosphere at 5atm, show that uncoated NG exhibits significantly higher weight gain than SiC-coated NG. The continuous and compact SiC coating exhibits excellent infiltration resistance in liquid fluoride salt as confirmed by synchrotron radiation X-ray microbeam fluorescence.
ISSN:0022-3115
1873-4820
DOI:10.1016/j.jnucmat.2014.01.034