Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane

doi:10.1016/j.jeurceramsoc.2017.09.031

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
发表期刊	JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
ISSN	0955-2219
卷号	38 期号:2 页码:453-462
文章类型	期刊论文
摘要	Modification 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.
关键词	Gas-cooled Reactor Htr Fuel-elements Molten-salt Matrix Graphite Xe-135 Penetration Ceramic Coatings Infiltration Temperature Stability Behavior
DOI	10.1016/j.jeurceramsoc.2017.09.031
收录类别	SCI
语种	英语
WOS记录号	WOS:000418211000008
引用统计
文献类型	期刊论文
条目标识符	http://ir.sinap.ac.cn/handle/331007/29112
专题	中科院上海应用物理研究所2011-2018年
作者单位	1.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
推荐引用方式 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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