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Stability analysis on flow parameters in coolant temperature control system of lead-cooled fast reactor
Yao, Yuantao1,2; Wang, Jianye1; Zhang, Junjun1; Yang, Minghan1
2019-04-01
发表期刊ANNALS OF NUCLEAR ENERGY
ISSN0306-4549
摘要

Lead-cooled Fast Reactor (LFR), one of the promising nuclear energy technologies for future advanced system, is well foreseen in meeting the goals of Generation IV fission reactor. In LFR, Coolant Temperature Control System (CTCS) is one of the critical parts, and the influence of coolant flow parameters on the stability analysis is worth investigating and studying. In this paper, we use the CLEAR-S, an integrated multifunctional non-nuclear test facility, as reference and the stability analysis of CTCS, concerned to coolant flow rate has been completed based on simplified coolant thermal circulation model. Location of eigen-values and calculation results of real stability radius, both qualitatively and quantitatively reflect the influence of coolant flow rate on stability respectively. The analysis results show that the feed-water flow rate in steady state is a critical parameter for CLEAR-S, because larger feed-water flow rate can improve stability apparently. However, LBE coolant flow rate has little impact on system stability. The results of this work will provide an effective reference for design and operation of LFR. (C) 2018 Elsevier Ltd. All rights reserved.

关键词Lead-cooled fast reactor Coolant temperature control system Coolant flow rate Stability analysis Real stability radius
DOI10.1016/j.anucene.2018.11.034
关键词[WOS]DESIGN
收录类别SCI
语种英语
资助项目strategic priority research program of the Chinese Academy of Sciences[XDA03040000]
项目资助者strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences ; strategic priority research program of the Chinese Academy of Sciences
WOS研究方向Nuclear Science & Technology
WOS类目Nuclear Science & Technology
WOS记录号WOS:000458944500033
出版者PERGAMON-ELSEVIER SCIENCE LTD
引用统计
被引频次:3[WOS]   [WOS记录]     [WOS相关记录]
文献类型期刊论文
条目标识符http://ir.hfcas.ac.cn:8080/handle/334002/42009
专题中国科学院核能安全技术研究所
通讯作者Yang, Minghan
作者单位1.Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Anhui, Peoples R China
2.Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China
第一作者单位中国科学院核能安全技术研究所
通讯作者单位中国科学院核能安全技术研究所
推荐引用方式
GB/T 7714
Yao, Yuantao,Wang, Jianye,Zhang, Junjun,et al. Stability analysis on flow parameters in coolant temperature control system of lead-cooled fast reactor[J]. ANNALS OF NUCLEAR ENERGY,2019,126(无):367-375.
APA Yao, Yuantao,Wang, Jianye,Zhang, Junjun,&Yang, Minghan.(2019).Stability analysis on flow parameters in coolant temperature control system of lead-cooled fast reactor.ANNALS OF NUCLEAR ENERGY,126(无),367-375.
MLA Yao, Yuantao,et al."Stability analysis on flow parameters in coolant temperature control system of lead-cooled fast reactor".ANNALS OF NUCLEAR ENERGY 126.无(2019):367-375.
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