Preliminary thermal-hydraulic sub-channel analysis of 61 wire-wrapped bundle cooled by lead bismuth eutectic

doi:10.1016/j.anucene.2016.01.034

CORC > 合肥物质科学研究院 > 中国科学院合肥物质科学研究院 > 中国科学院核能安全技术研究所

	Preliminary thermal-hydraulic sub-channel analysis of 61 wire-wrapped bundle cooled by lead bismuth eutectic
	Lyu, Kefeng 1,2,3; Chen, Liuli 2,3; Yue, Chenchong 2,3; Gao, Sheng 2,3; Zhou, Tao 2,3; Huang, Qunying 2,3
刊名	ANNALS OF NUCLEAR ENERGY
	2016-06-01
卷号	92 期号:无页码:243-250
关键词	Sub-channel Code Lead-bismuth Eutectic Fuel Pin Bundle Thermal-hydraulic
DOI	10.1016/j.anucene.2016.01.034
文献子类	Article
英文摘要	Lead bismuth eutectic (LBE) is one of the most promising materials for coolant and spallation target for Accelerator Driven Systems (ADS). The thermal-hydraulic features in fuel assembly are one of the most important issues for development of this system. Aiming to get a deeper understanding on heat transfer behavior of wire-wrapped bundle cooled by LBE and to support the design of ADS systems, a fuel bundle simulator with 61 electrical rods spaced by helical wire was developed in KYLIN-II facility. In this paper, the preliminary heat transfer experiments with 70 kW under forced and natural circulation regimes were performed. The thermal-hydraulic behaviors including thermal entrance characteristics, heat transfer coefficients, and temperature distribution at the cross section were investigated under both regimes. The experiments depict reasonable results, and the Nu based on center sub-channel shows an agreement with empirical correlations. Besides, a special sub-channel code named SACOS-PB was employed to support the sub-channel analysis; and similar results to each other were obtained. It can be concluded that the SACOS-PB is a reliable tool for LBE system sub-channel analysis. Based on the present work the comprehensive thermal-hydraulic analysis with a detailed test matrix in terms of different flow rates and ;heating powers will be conducted in near future. (C) 2016 Elsevier Ltd. All rights reserved.
WOS关键词	ANALYSIS CODE ; POOL ; REACTOR ; BARE ; FLOW
WOS研究方向	Nuclear Science & Technology
语种	英语
WOS记录号	WOS:000373655600023
资助机构	National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; 51301163) ; 51301163) ; 51301163) ; 51301163) ; 51301163) ; 51301163) ; 51301163) ; 51301163) ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; National Natural Science Foundations of China(51401205 ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; Chinese Academy of Sciences(XDA03040000) ; 51301163) ; 51301163) ; 51301163) ; 51301163) ; 51301163) ; 51301163) ; 51301163) ; 51301163)
内容类型	期刊论文
源URL	[http://ir.hfcas.ac.cn:8080/handle/334002/30899]
专题	合肥物质科学研究院_中国科学院核能安全技术研究所
作者单位	1.Univ Sci & Technol China, Hefei 230026, Peoples R China 2.Chinese Acad Sci, Inst Nucl Energy Safety Technol, Key Lab Neutron & Radiat Safety, Hefei 230031, Peoples R China 3.Jiangsu Higher Educ Inst, Collaborat Innovat Ctr Radiat Med, Suzhou 215006, Peoples R China
推荐引用方式 GB/T 7714	Lyu, Kefeng,Chen, Liuli,Yue, Chenchong,et al. Preliminary thermal-hydraulic sub-channel analysis of 61 wire-wrapped bundle cooled by lead bismuth eutectic[J]. ANNALS OF NUCLEAR ENERGY,2016,92(无):243-250.
APA	Lyu, Kefeng,Chen, Liuli,Yue, Chenchong,Gao, Sheng,Zhou, Tao,&Huang, Qunying.(2016).Preliminary thermal-hydraulic sub-channel analysis of 61 wire-wrapped bundle cooled by lead bismuth eutectic.ANNALS OF NUCLEAR ENERGY,92(无),243-250.
MLA	Lyu, Kefeng,et al."Preliminary thermal-hydraulic sub-channel analysis of 61 wire-wrapped bundle cooled by lead bismuth eutectic".ANNALS OF NUCLEAR ENERGY 92.无(2016):243-250.