Nuclear Engineering and Technology | 2019

Excluding molten fluoride salt from nuclear graphite by SiC/glassy carbon composite coating

 
 
 
 
 

Abstract


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\xa0atm was merely 0.26\xa0wt%, which was much less than that into virgin IG-110 under 1.5\xa0atm (13.5\xa0wt%) and the critical index proposed for nuclear graphite used in MSR (0.5\xa0wt%). 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.

Volume 51
Pages 1390-1397
DOI 10.1016/J.NET.2019.03.006
Language English
Journal Nuclear Engineering and Technology

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