Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating

  • He, Zhao (Key Laboratory of Carbon Materials, Institute of Coal Chemistry, Chinese Academy of Sciences) ;
  • Song, Jinliang (Key Laboratory of Nuclear Radiation and Nuclear Energy Technology, Shanghai Institute of Applied Physics, Chinese Academy of Sciences) ;
  • Lian, Pengfei (Key Laboratory of Carbon Materials, Institute of Coal Chemistry, Chinese Academy of Sciences) ;
  • Zhang, Dongqing (Key Laboratory of Carbon Materials, Institute of Coal Chemistry, Chinese Academy of Sciences) ;
  • Liu, Zhanjun (Key Laboratory of Carbon Materials, Institute of Coal Chemistry, Chinese Academy of Sciences)
  • Received : 2018.09.23
  • Accepted : 2019.03.07
  • Published : 2019.06.25
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Abstract

SiC coating and SiC/glassy carbon composite coating were prepared on IG-110 nuclear graphite (Toyo Tanso Co., Ltd., Japan) to strengthen its inertness to molten fluoride salt used in molten salt reactor (MSR). Two kinds of modified graphite were obtained and correspondingly named as IG-110-1 and IG-110-2, which referred to modified IG-110 with a single SiC coating and a SiC/glassy carbon composite coating, respectively. Both structure and property of modified graphite were carefully researched and contrasted with virgin IG-110. Results indicated that modified graphite presented better comprehensive properties such as more compact structure and higher resistance to molten salt infiltration. With the protection of coatings, the infiltration amounts of fluoride salt into modified graphite were much less than that into virgin IG-110 at the same circumstance. Especially, the infiltration amount of fluoride salt into IG-110-2 under 5 atm was merely 0.26 wt%, which was much less than that into virgin IG-110 under 1.5 atm (13.5 wt%) and the critical index proposed for nuclear graphite used in MSR (0.5 wt%). The SiC/glassy carbon composite coating gave rise to highest resistance to molten salt infiltration into IG-110-2, and thus demonstrated it could be a promising protective coating for nuclear graphite used in MSR.

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References

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