Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR

doi:10.1016/j.fusengdes.2020.112098

	Neutronics analysis of thorium-uranium based molten salt blanket in stellarator-type FFHR
	Li, Jin-Yang 2,4,5; Gu, Long 2,5; Xu, Hu-Shan 2,4,5; Zhang, You-Peng 3; Dai, Yong 1; Yao, Cun-Feng 5; Yu, Rui 2,5; Zhang, Lu 5; Jiang, Wei 5
刊名	FUSION ENGINEERING AND DESIGN
	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.
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关键词	SYSTEM ; DESIGN ; OPENMC ; CAD
WOS研究方向	Nuclear Science & Technology
语种	英语
出版者	ELSEVIER SCIENCE SA
WOS记录号	WOS:000680832500007
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
内容类型	期刊论文
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.