Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR
文献类型：期刊论文
| 作者 | Li, Jin-Yang2,4,5 ; Gu, Long2,5; Xu, Hu-Shan2,4,5; Zhang, You-Peng3; Dai, Yong1; Yao, Cun-Feng5; Yu, Rui2,5; Zhang, Lu5; Jiang, Wei5
|
| 刊名 | FUSION ENGINEERING AND DESIGN
 |
| 出版日期 | 2021 |
| 卷号 | 162页码:8 |
| 关键词 | Neutronics design CAD Stellarator Fusion-Fission TBR |
| ISSN号 | 0920-3796 |
| DOI | 10.1016/j.fusengdes.2020.112098 |
| 通讯作者 | Gu, Long(gulong@impcas.ac.cn) |
| 英文摘要 | The stellarator-type Fusion-Fission Hybrid Reactor (FFHR) is an alternative conceptual design for the tokamakbased devices in order to realize the stable power output. It can bring the viable energy source for the fusion technology in a foreseeable future, and has been widely studied with a lot of advanced concepts being proposed. However, there are some challenges in the neutronics design of the FFHR blanket for the purpose of obtaining the appropriate Tritium Breeding Ratio (TBR) and blanket energy multiplication factor, since the blanket system has a complicated three-dimensional structure in helical shape, which can not be easily translated into native geometry representation syntax of most Monte Carlo neutron transport codes. In this paper, a liquid fuel, F-Li-Be molten salt, with uranium and thorium dissolved has been proposed for the preliminary design of stellarator-type FFHR blanket. Besides, the CAD-PSFO code [19] has been employed for the simulation of complex geometry structure in the helical blanket, and the OMCB package [22] has been used in the burnup analysis of the neutronics features in the molten salt blanket. Moreover, detailed geometry design of the blanket arrangement and thickness have been studied in order to meet the requirement of energy multiplication factor in the stellarator-type FFHR. Also, the composition and concentration of the fuel material and Li-6 in molten salt have been discussed for the purpose of tritium self-sufficiency with steady energy supply in the whole lifetime. |
| WOS关键词 | SYSTEM ; DESIGN ; OPENMC ; CAD |
| 资助项目 | funds of Light of West China type B[E0233501Y] ; The main equipment, key materials, technology research, development and application of the fourth generation lead based fast reactor[Y9391601] |
| WOS研究方向 | Nuclear Science & Technology |
| 语种 | 英语 |
| WOS记录号 | WOS:000680832500007 |
| 出版者 | ELSEVIER SCIENCE SA |
| 资助机构 | funds of Light of West China type B ; The main equipment, key materials, technology research, development and application of the fourth generation lead based fast reactor |
| 源URL | [http://119.78.100.186/handle/113462/136684]  |
| 专题 | 中国科学院近代物理研究所 |
| 通讯作者 | Gu, Long |
| 作者单位 | 1.Paul Scherrer Inst, CH-5232 Villigen, Switzerland 2.Univ Chinese Acad Sci, Sch Nucl Sci & Technol, Beijing 100049, Peoples R China 3.Fudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China 4.Adv Energy Sci & Technol Guangdong Lab, Huizhou 516002, Peoples R China 5.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China |
| 推荐引用方式 GB/T 7714 | Li, Jin-Yang,Gu, Long,Xu, Hu-Shan,et al. Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR[J]. FUSION ENGINEERING AND DESIGN,2021,162:8. |
| APA | Li, Jin-Yang.,Gu, Long.,Xu, Hu-Shan.,Zhang, You-Peng.,Dai, Yong.,...&Jiang, Wei.(2021).Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR.FUSION ENGINEERING AND DESIGN,162,8. |
| MLA | Li, Jin-Yang,et al."Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR".FUSION ENGINEERING AND DESIGN 162(2021):8. |
入库方式： OAI收割
来源：近代物理研究所
浏览0
下载0
收藏0
其他版本
除非特别说明，本系统中所有内容都受版权保护，并保留所有权利。