Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel

doi:10.1007/s41365-017-0321-9

CORC > 上海应用物理研究所 > 中国科学院上海应用物理研究所 > 中科院上海应用物理研究所2011-2017年

	Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel
	Peng, Y; Zhu, GF; Zou, Y; Liu, SJ; Xu, HJ
刊名	NUCLEAR SCIENCE AND TECHNIQUES
	2017
卷号	28 期号:11 页码:-
关键词	Molten-salt Thorium Performance
ISSN号	1001-8042
DOI	10.1007/s41365-017-0321-9
文献子类	期刊论文
英文摘要	Fast reactors based on thorium fuel have enhanced inherent safety. Fluoride salt performs well as a coolant in high-temperature nuclear systems. In this paper, we present a reference core for a large fluoride-salt-cooled solid-fuel fast reactor (LSFR) using thorium-uranium fuel cycle. Neutronics physics of the LSFR reference core is investigated with 2D and 3D in-core fuel management strategy. The design parameters analyzed include the fuel volume fraction, power density level and continuous removal of fission products with 3D fuel shuffling that obtains better equilibrium core performance than 2D shuffling. A self-sustained core is achieved for all cases, and the core of 60% fuel volume fraction at 50 MW/m(3) power density is of the best breeding performance (average breeding ratio 1.134). The LSFR core based on thorium fuel is advantageous in its high discharge burn-up of 20-30% fissions per initial heavy metal atom, small reactivity swing over the whole lifetime (to simplify the reactivity control system), the negative reactivity temperature coefficient (intrinsically safe for all cases) and accepted cladding peak radiation damage. The LSFR reactor is a good alternative option for the deployment of a self-sustained thorium-based nuclear system.
WOS关键词	MOLTEN-SALT ; THORIUM ; PERFORMANCE
语种	英语
WOS记录号	WOS:000417222800005
内容类型	期刊论文
源URL	[http://ir.sinap.ac.cn/handle/331007/28746]
专题	上海应用物理研究所_中科院上海应用物理研究所2011-2017年
推荐引用方式 GB/T 7714	Peng, Y,Zhu, GF,Zou, Y,et al. Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel[J]. NUCLEAR SCIENCE AND TECHNIQUES,2017,28(11):-.
APA	Peng, Y,Zhu, GF,Zou, Y,Liu, SJ,&Xu, HJ.(2017).Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel.NUCLEAR SCIENCE AND TECHNIQUES,28(11),-.
MLA	Peng, Y,et al."Neutronics physics analysis of a large fluoride-salt-cooled solid-fuel fast reactor with Th-based fuel".NUCLEAR SCIENCE AND TECHNIQUES 28.11(2017):-.