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
ISSN0149-1970
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
DOI10.1016/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
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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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