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
2017
发表期刊NUCLEAR SCIENCE AND TECHNIQUES
ISSN1001-8042
卷号28期号:11页码:-
文章类型期刊论文
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.
关键词Molten-salt Thorium Performance
DOI10.1007/s41365-017-0321-9
关键词[WOS]MOLTEN-SALT ; THORIUM ; PERFORMANCE
收录类别SCI
语种英语
WOS记录号WOS:000417222800005
引用统计
文献类型期刊论文
条目标识符http://ir.sinap.ac.cn/handle/331007/28746
专题中科院上海应用物理研究所2011-2018年
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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):-.
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