Study on the hydraulic performance of the axial flow main coolant pump for lead-cooled fast reactor

doi:10.1016/j.nucengdes.2023.112375

	Study on the hydraulic performance of the axial flow main coolant pump for lead-cooled fast reactor
	Guo, Yanlei1,2,4 ; Yang, Congxin1,2 ; Wang, Yan 3; Lv, Tianzhi 1,2
	2023-08-15
在线发表时间	2023-05
发表期刊	NUCLEAR ENGINEERING AND DESIGN
ISSN	0029-5493
卷号	410
摘要	Lead-cooled fast reactor (LFR) has been listed as the most promising fourth-generation reactor type for commercial applications. LFR uses liquid heavy metal, lead or lead-bismuth eutectic alloy (LBE) as the coolant. It has completely different physical parameters such as the density and viscosity from the traditional nuclear reactor coolant, water. Different physical parameters will have a noticeable effect on the hydraulic performance of the main coolant pump. In this study, based on SST k-w turbulence model, an axial flow main coolant pump in the LFR at multiple working conditions was simulated, and the differences of its hydraulic performance under LBE and water and the reasons were analyzed in detail. Both the head and efficiency of the axial flow pump model under LBE are higher obviously than that under water, and the theoretical head is basically the same under the two mediums. The increase of the head and efficiency under LBE mainly results from the decrease of profile losses in the impeller and guide vane, both the friction loss and losses due to vortices in the boundary layer and wake formation at the outlet of the blade are obviously smaller than that under water.
关键词	Lead -cooled fast reactor Hydraulic loss Friction shear stress Turbulent kinetic energy Reynolds number
DOI	10.1016/j.nucengdes.2023.112375
收录类别	SCIE ; EI
语种	英语
WOS研究方向	Nuclear Science & Technology
WOS类目	Nuclear Science & Technology
WOS记录号	WOS:000999706500001
出版者	ELSEVIER SCIENCE SA
EI入藏号	20232014105070
EI主题词	Shear stress
EI分类号	443.1 Atmospheric Properties ; 531 Metallurgy and Metallography ; 549.3 Nonferrous Metals and Alloys excluding Alkali and Alkaline Earth Metals ; 618.2 Pumps ; 631.1 Fluid Flow, General ; 641.1 Thermodynamics ; 803 Chemical Agents and Basic Industrial Chemicals ; 931 Classical Physics ; Quantum Theory ; Relativity
来源库	WOS
原始文献类型	Article
引用统计	被引频次[WOS]：0 [WOS记录] [WOS相关记录]
文献类型	期刊论文
条目标识符	https://ir.lut.edu.cn/handle/2XXMBERH/162091
专题	能源与动力工程学院
作者单位	1.Lanzhou Univ Technol, Sch Energy & Power Engn, Lanzhou 730050, Peoples R China; 2.Key Lab Fluid Machinery & Syst, Lanzhou 730050, Peoples R China; 3.Nucl Power Inst China, Chengdu 610213, Peoples R China; 4.287 Langongping Rd, Lanzhou, Gansu, Peoples R China
第一作者单位	能源与动力工程学院
第一作者的第一单位	能源与动力工程学院
推荐引用方式 GB/T 7714	Guo, Yanlei,Yang, Congxin,Wang, Yan,et al. Study on the hydraulic performance of the axial flow main coolant pump for lead-cooled fast reactor[J]. NUCLEAR ENGINEERING AND DESIGN,2023,410.
APA	Guo, Yanlei,Yang, Congxin,Wang, Yan,&Lv, Tianzhi.(2023).Study on the hydraulic performance of the axial flow main coolant pump for lead-cooled fast reactor.NUCLEAR ENGINEERING AND DESIGN,410.
MLA	Guo, Yanlei,et al."Study on the hydraulic performance of the axial flow main coolant pump for lead-cooled fast reactor".NUCLEAR ENGINEERING AND DESIGN 410(2023).