Neutronic study of a combined fast fission FFHR and thermal fission FFHR system using thorium bearing molten salt fuel
文献类型：期刊论文
| 作者 | Xiao, S. C.1; Zhao, J.1 ; Zhou, Z.1; Yang, Y.2
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| 刊名 | ANNALS OF NUCLEAR ENERGY
 |
| 出版日期 | 2018-02-01 |
| 卷号 | 112页码:666-672 |
| 关键词 | Fast breeder Thermal burner U-233 breeding Th-U cycle Molten salt fuel |
| ISSN号 | 0306-4549 |
| DOI | 10.1016/j.anucene.2017.11.001 |
| 英文摘要 | In this paper, an integrated fusion-fission hybrid reactor energy system aiming at utilizing the thorium fuel efficiently with Th-U closed cycle is presented. The ultimate purpose is transition to the all thorium fueled energy system with the bred U-233 fuel burning in-site. The system consists of two fusion-fission hybrid reactors. The first reactor is a fast breeder which provides the starting fuel U-233 for the second reactor (thermal burner). The bred U-233 is burnt in the second reactor with the thorium bearing molten salt fuel blanket. In order to reach the multi-system performance, i.e. high energy multiplication M, tritium self-sufficiency and fissile fuel self-sufficiency, using limiting U-233 start fuel, the seed-blanket concept is adopted in the thermal burner design. The thermal burner blanket is divided into two main regions. The front region (seed) plays the dominate role in the energy production, neutron multiplication and U-233 breeding. Excess neutrons produced by the front region are then used to drive backward region (blanket) to breed tritium. The Couple 2.0 code developed by Tsinghua University is used to calculate the fuel depletion process of the whole system. The simulated results show, the thermal burner could operate with excellent performance, energy multiplication M (8-10), tritium breeding ratio TBR (> 1.05) continuously and only natural thorium fuel is added into the system. (C) 2017 Elsevier Ltd. All rights reserved. |
| 资助项目 | Chinese magnetic confined nuclear fusion energy research[2010GB111006] ; National Natural Science Foundation of China[11305092] |
| WOS研究方向 | Nuclear Science & Technology |
| 语种 | 英语 |
| WOS记录号 | WOS:000419409100057 |
| 出版者 | PERGAMON-ELSEVIER SCIENCE LTD |
| 资助机构 | Chinese magnetic confined nuclear fusion energy research ; National Natural Science Foundation of China |
| 源URL | [http://119.78.100.186/handle/113462/46220]  |
| 专题 | 中国科学院近代物理研究所 |
| 通讯作者 | Xiao, S. C. |
| 作者单位 | 1.Tsinghua Univ, Inst Nucl & New Energy Technol, Beijing, Peoples R China 2.Chinese Acad Sci, Inst Modern Phys, Lanzhou, Gansu, Peoples R China |
| 推荐引用方式 GB/T 7714 | Xiao, S. C.,Zhao, J.,Zhou, Z.,et al. Neutronic study of a combined fast fission FFHR and thermal fission FFHR system using thorium bearing molten salt fuel[J]. ANNALS OF NUCLEAR ENERGY,2018,112:666-672. |
| APA | Xiao, S. C.,Zhao, J.,Zhou, Z.,&Yang, Y..(2018).Neutronic study of a combined fast fission FFHR and thermal fission FFHR system using thorium bearing molten salt fuel.ANNALS OF NUCLEAR ENERGY,112,666-672. |
| MLA | Xiao, S. C.,et al."Neutronic study of a combined fast fission FFHR and thermal fission FFHR system using thorium bearing molten salt fuel".ANNALS OF NUCLEAR ENERGY 112(2018):666-672. |
入库方式： OAI收割
来源：近代物理研究所
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