Neutronic study of an innovative natural uranium-thorium based fusion-fission hybrid energy system
文献类型：期刊论文
| 作者 | Xiao, S. C.1; Zhao, J.1; Zhou, Z.1; Yang, Y.2 |
| 刊名 | ANNALS OF NUCLEAR ENERGY
 |
| 出版日期 | 2014-11-01 |
| 卷号 | 73页码:500-505 |
| ISSN号 | 0306-4549 |
| 关键词 | Ffhr U-modules Th-modules U-233 Breeding Optimization |
| DOI | 10.1016/j.anucene.2014.07.032 |
| 文献子类 | Article |
| 英文摘要 | An innovative design for a water cooled fusion-fission hybrid reactor (FFHR), aiming at efficiently utilizing natural uranium and thorium resources, is presented. The major objective is to study the feasibility of this concept balanced with multi-purposes, including energy gain, tritium breeding and U-233 breeding. In order to improve overall neutron economy of the system, the fission blanket is designed with two types of modules, i.e. the natural uranium modules (U-modules) and thorium modules (Th-modules), which are alternately arranged in the toroidal and poloidal directions of the blanket. This innovative design is based on a simple intuition of neutron distribution: with the alternate geometrical arrangement, energy multiplication by uranium fission, tritium breeding and U-233 breeding are performed separately in different sub-zones in the blanket. The uranium modules which has excellent neutron economy under the combined neutron spectrum, plays the dominant role in the energy production, neutron multiplication and tritium breeding. Excess neutrons produced by the uranium modules are then used to drive the thorium modules (which have poor neutron economy) to breed U-233 fuel. Therefore, it creates a new free dimension to realize the blanket's balanced design. The COUPLE code developed by INET of Tsinghua University is used to simulate the neutronic behavior in the blanket. The simulated results show that with the volumetric ratio of thorium modules about 0.4, the balanced design for multi purposes is achievable, with energy multiplication M >= 9, tritium breeding ratio TBR >= 1.05, and at the end of the five years refueling cycle, the U-233 enrichment in thorium modules exceeding 1.0%. The neutronic analysis results also show that the preliminary design of this innovative FFHR is of great potential to utilize the bred U-233 effectively after the initial fuel load of the first ten-year operation. (C) 2014 Elsevier Ltd. All rights reserved. |
| 资助项目 | Chinese magnetic confined nuclear fusion energy research[2010GB111006] |
| WOS研究方向 | Nuclear Science & Technology |
| 语种 | 英语 |
| 出版者 | PERGAMON-ELSEVIER SCIENCE LTD |
| WOS记录号 | WOS:000342248400052 |
| 源URL | [http://119.78.100.186/handle/113462/49303]  |
| 专题 | 中国科学院近代物理研究所 |
| 通讯作者 | Zhou, Z. |
| 作者单位 | 1.Tsinghua Univ, Inst Nucl & New Energy Technol, Beijing 100084, Peoples R China 2.Chinese Acad Sci, Inst Modern Phys, Lanzhou, Peoples R China |
| 推荐引用方式 GB/T 7714 | Xiao, S. C.,Zhao, J.,Zhou, Z.,et al. Neutronic study of an innovative natural uranium-thorium based fusion-fission hybrid energy system[J]. ANNALS OF NUCLEAR ENERGY,2014,73:500-505. |
| APA | Xiao, S. C.,Zhao, J.,Zhou, Z.,&Yang, Y..(2014).Neutronic study of an innovative natural uranium-thorium based fusion-fission hybrid energy system.ANNALS OF NUCLEAR ENERGY,73,500-505. |
| MLA | Xiao, S. C.,et al."Neutronic study of an innovative natural uranium-thorium based fusion-fission hybrid energy system".ANNALS OF NUCLEAR ENERGY 73(2014):500-505. |
入库方式： OAI收割
来源：近代物理研究所
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