| Oxidation performance of graphite material in reactors | |
| Xiaowei Luo ; Xinli Yu ; Suyuan Yu | |
| 2010-10-12 ; 2010-10-12 | |
| 关键词 | Practical/ fission reactor cooling fission reactor safety graphite oxidation/ oxidation graphite material high temperature gas-cooled reactor/ A2850I Gas cooled reactors A2844 Fission reactor protection systems, safety and accidents A8160 Corrosion, oxidation, etching, and other surface treatments A8120V Preparation of fullerenes and fullerene-related materials, intercalation compounds, and diamond |
| 中文摘要 | Graphite is used as a structural material and moderator for high temperature gas-cooled reactors (HTGR). When a reactor is in operation, graphite oxidation influences the safety and operation of the reactor because of the impurities in the coolant and/or the accident conditions, such as water ingress and air ingress. In this paper, the graphite oxidation process is introduced, factors influencing graphite oxidation are analyzed and discussed, and some new directions for further study are pointed out. |
| 语种 | 英语 |
| 出版者 | Springer ; China |
| 内容类型 | 期刊论文 |
| 源URL | [http://hdl.handle.net/123456789/79353]  |
| 专题 | 清华大学 |
| 推荐引用方式 GB/T 7714 | Xiaowei Luo,Xinli Yu,Suyuan Yu. Oxidation performance of graphite material in reactors[J],2010, 2010. |
| APA | Xiaowei Luo,Xinli Yu,&Suyuan Yu.(2010).Oxidation performance of graphite material in reactors.. |
| MLA | Xiaowei Luo,et al."Oxidation performance of graphite material in reactors".(2010). |
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