The feasibility research of thorium breeding using fluoride salt as a fast reactor coolant

doi:10.1016/j.pnucene.2017.08.003

CAS OpenIR > 中科院上海应用物理研究所2011-2018年

	The feasibility research of thorium breeding using fluoride salt as a fast reactor coolant
	Peng, Y; Zhu, GF; Zou, Y; Liu, YF; Yu, XH; Cai, XZ; Xu, HJ
	2017
发表期刊	PROGRESS IN NUCLEAR ENERGY
ISSN	0149-1970
卷号	101 期号:-页码:199-208
文章类型	期刊论文
摘要	Breeder reactors are considered as a unique tool for fully exploiting natural resources. Fast breeder reactors based on thorium fuel can enhance inherent safety. Fluoride salt has good performance as a coolant in high-temperature nuclear systems. However, there is some doubt about the fuel breeding ability using fluoride salt coolant for fast spectrum due to its moderating ability. The aim of this study was to choose a proper fluoride salt mixture for Liquid-salt-cooled Solid-fuel Fast Reactor (LSFR) based on thorium-uranium fuel and give parametric studies to provide a design window for flexible self-sustaining core design. Infinite assembly model was used to analyze the salt selection from five candidate fluorides for fast spectrum as coolant. Combining neutron balance analysis with linear least squares fitting method based on OD model, parametric studies at the neutron balance equation unique solution with burn-up for several parameters such as fuel volume fraction, removing fission gases process, total neutron losses and power density were presented in this paper. It was found that BeF2-NaF was a promising coolant in the five candidate fluoride salt mixture. This study proved that the design of a self-sustaining core for fluoride-salt-cooled fast breeder based on thorium fuel is achievable. A design window was found in the definition of a self-sustaining core for various fuel volume fractions and neutron loss fractions. Core design and fuel management strategy will be given in future. (c) 2017 Elsevier Ltd. All rights reserved.
关键词	Burn Reactors Fuel-cycle Sustainability Perspectives
DOI	10.1016/j.pnucene.2017.08.003
关键词[WOS]	BURN REACTORS ; FUEL-CYCLE ; SUSTAINABILITY ; PERSPECTIVES
收录类别	SCI
语种	英语
WOS记录号	WOS:000412261300003
引用统计
文献类型	期刊论文
条目标识符	http://ir.sinap.ac.cn/handle/331007/28862
专题	中科院上海应用物理研究所2011-2018年
推荐引用方式 GB/T 7714	Peng, Y,Zhu, GF,Zou, Y,et al. The feasibility research of thorium breeding using fluoride salt as a fast reactor coolant[J]. PROGRESS IN NUCLEAR ENERGY,2017,101(-):199-208.
APA	Peng, Y.,Zhu, GF.,Zou, Y.,Liu, YF.,Yu, XH.,...&Xu, HJ.(2017).The feasibility research of thorium breeding using fluoride salt as a fast reactor coolant.PROGRESS IN NUCLEAR ENERGY,101(-),199-208.
MLA	Peng, Y,et al."The feasibility research of thorium breeding using fluoride salt as a fast reactor coolant".PROGRESS IN NUCLEAR ENERGY 101.-(2017):199-208.

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