中国科学院机构知识库网格
Chinese Academy of Sciences Institutional Repositories Grid
Neutronics Analysis of the Stellarator-Type Fusion-Fission Hybrid Reactor Using Mesh Simplification

文献类型:期刊论文

作者Li, Jin-Yang1,4,5; Guo, Sheng-Miao1,4; Gu, Long1,3,4; Zhang, You-Peng2; Xu, Hu-Shan1,4; Wang, Da-Wei1,3; Yu, Rui1,4; Wang, Guan1,4
刊名FUSION SCIENCE AND TECHNOLOGY
出版日期2021-05-28
页码10
ISSN号1536-1055
关键词Stellarator-type FFHR mesh oriented computer-aided design burnup transmutation
DOI10.1080/15361055.2021.1921363
通讯作者Gu, Long(gulong@impcas.ac.cn)
英文摘要The stellarator plasma device has been widely studied as one of the candidate solutions paralleling the ITER project, and its coupling with a fission blanket can bring benefits promoting the development of fusion technology with stable energy production simultaneously. However, the neutronics optimization design for the stellarator-type Fusion-Fission Hybrid Reactor (FFHR) is extremely complex since the helical structure with a large amount of spline curved surfaces cannot be exactly described in most of the Monte Carlo simulation processes, and the preliminary design stage has also been a time-consuming and error-prone task with the requirements frequently changing. In this context, the mesh-oriented optimized method has been considered for the parametric modeling analysis in order to get the ideal structure without redundant topologic information, and the corresponding conversion process from computer-aided design (CAD) to Monte Carlo simulation has been fulfilled by the CAD-PSFO code. Moreover, the liquid type of thorium-uranium fuels has been selected as the solutes dissolve in the molten salt blanket with its multilayer structure, where the burnup feature and neutronics properties have been analyzed and explained with the help of the OMCB code. The stellarator-type FFHR has been designed as a compact multifunctional device that can incinerate plutonium and transmute the minor actinide isotopes with tritium self-sufficiency and the high-energy multiplication factor.
WOS关键词CAD ; TRANSMUTATION ; TRANSPORT ; SYSTEM ; FUEL
资助项目[E023351Y] ; [Y9391601] ; [2020YFB1902100]
WOS研究方向Nuclear Science & Technology
语种英语
出版者TAYLOR & FRANCIS INC
WOS记录号WOS:000654978700001
源URL[http://119.78.100.186/handle/113462/137319]  
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.Chinese Acad Sci, Inst Modern Phys, Lanzhou 730000, Peoples R China
2.Fudan Univ, Inst Modern Phys, Shanghai 200433, Peoples R China
3.Lanzhou Univ, Sch Nucl Sci & Technol, Lanzhou 730000, Peoples R China
4.Univ Chinese Acad Sci, Sch Nucl Sci & Technol, Beijing 100049, Peoples R China
5.Adv Energy Sci & Technol Guangdong Lab, Huizhou 516002, Peoples R China
推荐引用方式
GB/T 7714
Li, Jin-Yang,Guo, Sheng-Miao,Gu, Long,et al. Neutronics Analysis of the Stellarator-Type Fusion-Fission Hybrid Reactor Using Mesh Simplification[J]. FUSION SCIENCE AND TECHNOLOGY,2021:10.
APA Li, Jin-Yang.,Guo, Sheng-Miao.,Gu, Long.,Zhang, You-Peng.,Xu, Hu-Shan.,...&Wang, Guan.(2021).Neutronics Analysis of the Stellarator-Type Fusion-Fission Hybrid Reactor Using Mesh Simplification.FUSION SCIENCE AND TECHNOLOGY,10.
MLA Li, Jin-Yang,et al."Neutronics Analysis of the Stellarator-Type Fusion-Fission Hybrid Reactor Using Mesh Simplification".FUSION SCIENCE AND TECHNOLOGY (2021):10.

入库方式: OAI收割

来源:近代物理研究所

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