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| 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 Publication | JOURNAL OF THE EUROPEAN CERAMIC SOCIETY
 |
| ISSN | 0955-2219 |
| Volume | 38Issue:2Pages:453-462 |
| Subtype | 期刊论文 |
| Abstract | 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. |
| Keyword | 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 |
| Indexed By | SCI |
| Language | 英语 |
| WOS ID | WOS:000418211000008 |
| Citation statistics | |
| Document Type | 期刊论文 |
| Identifier | http://ir.sinap.ac.cn/handle/331007/29112 |
| Collection | 中科院上海应用物理研究所2011-2020年 |
| Affiliation | 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 |
| 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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| Protecting nuclear g（5838KB） | 期刊论文 | 作者接受稿 | 开放获取 | CC BY-NC-SA | View Download | |
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