CAS OpenIR  > 中科院上海应用物理研究所2011-2018年
Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane
He, Z; Lian, PF; Song, Y; Liu, ZJ; Song, JL; Zhang, JP; Ren, XB; Feng, J; Yan, X; Guo, QG; Liu, WH
2018
Source PublicationJOURNAL OF THE EUROPEAN CERAMIC SOCIETY
ISSN0955-2219
Volume38Issue:2Pages:453-462
Subtype期刊论文
AbstractModification process has been conducted on commercial nuclear graphite IG-110 (Toyo Tanso Co., Ltd., Japan) by impregnation and pyrolysis of polycarbosilane (PCS) solution for getting the modified IG-110 (M-IG-110) coated by dense SiC coating for molten salt reactor. The microstructure and properties of graphite were systematically investigated and compared before and after the modification process. Results indicated that the MIG-110 possessed of more excellent integrated properties including molten salt barrier property and oxidation resistance than bare IG-110 due to the filling effect of SiC particles in the pores of M-IG-110 and dense SiC coating adhering to the surface of M-IG-110. The fluoride salt infiltration amount of M-IG-110 under 5 atm was only 1.1 wt%, which was much less than 14.9 wt% for bare IG-110. The SiC coating derived from PCS exhibited remarkable compatibility with graphite substrate under high temperature and gave rise to excellent oxidation resistance of M-IG-110.
KeywordGas-cooled Reactor Htr Fuel-elements Molten-salt Matrix Graphite Xe-135 Penetration Ceramic Coatings Infiltration Temperature Stability Behavior
DOI10.1016/j.jeurceramsoc.2017.09.031
Indexed BySCI
Language英语
WOS IDWOS:000418211000008
Citation statistics
Cited Times:11[WOS]   [WOS Record]     [Related Records in WOS]
Document Type期刊论文
Identifierhttp://ir.sinap.ac.cn/handle/331007/29112
Collection中科院上海应用物理研究所2011-2018年
Affiliation1.He, Z
2.Lian, PF
3.Song, Y
4.Liu, ZJ
5.Song, JL
6.Zhang, JP
7.Ren, XB
8.Feng, J
9.Yan, X
10.Guo, QG
11.Liu, WH
Recommended Citation
GB/T 7714
He, Z,Lian, PF,Song, Y,et al. Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane[J]. JOURNAL OF THE EUROPEAN CERAMIC SOCIETY,2018,38(2):453-462.
APA He, Z.,Lian, PF.,Song, Y.,Liu, ZJ.,Song, JL.,...&Liu, WH.(2018).Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane.JOURNAL OF THE EUROPEAN CERAMIC SOCIETY,38(2),453-462.
MLA He, Z,et al."Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane".JOURNAL OF THE EUROPEAN CERAMIC SOCIETY 38.2(2018):453-462.
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