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

doi:10.1016/j.jeurceramsoc.2017.09.031

	Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane
	He, Zhao 1,3; Lian, Pengfei 1; Song, Yan 1; Liu, Zhanjun 1; Song, Jinliang 2; Zhang, Junpeng 1; Ren, Xiaobo 1,3; Feng, Jing 1,3; Yan, Xi 1; Guo, Quangui 1
刊名	Journal of the European Ceramic Society
	2018
卷号	38 期号:2 页码:453-462
ISSN号	09552219
DOI	10.1016/j.jeurceramsoc.2017.09.031
英文摘要	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 M-IG-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. © 2017 Elsevier Ltd
出版者	Elsevier Ltd
内容类型	期刊论文
源URL	[http://ir.sic.ac.cn/handle/331005/25222]
专题	中国科学院上海硅酸盐研究所
作者单位	1.Key Laboratory of Carbon Materials, Institute of Coal Chemistry, Chinese Academy of Sciences, Taiyuan; 030001, China; 2.Key Laboratory of Nuclear Radiation and Nuclear Energy Technology, Shanghai Institute of Applied Physics, Chinese Academy of Sciences, Shanghai; 201800, China; 3.University of Chinese Academy of Sciences, Beijing; 100049, China
推荐引用方式 GB/T 7714	He, Zhao,Lian, Pengfei,Song, Yan,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, Zhao.,Lian, Pengfei.,Song, Yan.,Liu, Zhanjun.,Song, Jinliang.,...&Liu, Wenhong.(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, Zhao,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.