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Protecting nuclear graphite from liquid fluoride salt and oxidation by SiC coating derived from polycarbosilane
He, Zhao1,3; Lian, Pengfei1; Song, Yan1; Liu, Zhanjun1; Song, Jinliang2; Zhang, Junpeng1; Ren, Xiaobo1,3; Feng, Jing1,3; Yan, Xi1; Guo, Quangui1; Liu, Wenhong1
2018
Source PublicationJournal of the European Ceramic Society
ISSN09552219
Volume38Issue:2Pages:453-462
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 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
DOI10.1016/j.jeurceramsoc.2017.09.031
PublisherElsevier Ltd
EI KeywordsSilicon carbide
EI Classification Number539.1 Metals Corrosion - 804.2 Inorganic Compounds - 813.2 Coating Materials - 815.1.2 Inorganic Polymers
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Document Type期刊论文
Identifierhttp://ir.sic.ac.cn/handle/331005/25222
Collection中国科学院上海硅酸盐研究所
Affiliation1.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
Recommended Citation
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.
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