Thermo-Fluid-Solid Coupling Analysis on the Hot Water Pipeline in the Nuclear Reactor Water System

doi:10.1007/s11223-024-00653-5

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	Thermo-Fluid-Solid Coupling Analysis on the Hot Water Pipeline in the Nuclear Reactor Water System
	Sun, Z. J.1; Dai, J. T.2; Liu, H. D.2; Qu, L. F.3
	2024-07-29
发表期刊	STRENGTH OF MATERIALS
ISSN	0039-2316
摘要	This paper proposed a modeling method of the thermo-fluid-solid coupling simulation for the hot water pipeline with the insulation layer outside in the nuclear reactor. The temperature and stress distributions are analyzed and compared with the tests; the effects of the insulation layer thickness and support interval are investigated. The maximum stress occurs at the support points. The maximum stress increases approximately linearly with the increase of the support interval. The maximum deflection occurs at the middle of the two supports. The maximum deflection increases rapidly with the increase of the support interval, which is approximately in a parabolic relationship. The axial elongation ratio increases with the insulation layer thickness. The simulation results agree with the test results very well with regard of both stress and temperature distributions. The simulation method can also be used for the stress and temperature analysis in various cases, such as chemical-vessel and gas-oil pipeline with various thermal fluids inside.
关键词	thermo-fluid-solid coupling simulation hot water pipeline nuclear reactor temperature and stress distributions
其他关键词	CONJUGATED HEAT-TRANSFER
DOI	10.1007/s11223-024-00653-5
收录类别	SCIE
语种	英语
WOS研究方向	Materials Science
WOS类目	Materials Science, Characterization & Testing
WOS记录号	WOS:001279229900001
出版者	SPRINGER
原始文献类型	Article ; Early Access
EISSN	1573-9325
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	http://ir.library.ouchn.edu.cn/handle/39V7QQFX/171569
专题	国家开放大学
通讯作者	Sun, Z. J.
作者单位	1.Open Univ China, Engn Coll, Beijing, Peoples R China; 2.Naval Aviat Univ, Qingdao Campus, Qingdao, Peoples R China; 3.Third Mil Representat Off Army Chengdu, Chengdu, Peoples R China
推荐引用方式 GB/T 7714	Sun, Z. J.,Dai, J. T.,Liu, H. D.,et al. Thermo-Fluid-Solid Coupling Analysis on the Hot Water Pipeline in the Nuclear Reactor Water System[J]. STRENGTH OF MATERIALS,2024.
APA	Sun, Z. J.,Dai, J. T.,Liu, H. D.,&Qu, L. F..(2024).Thermo-Fluid-Solid Coupling Analysis on the Hot Water Pipeline in the Nuclear Reactor Water System.STRENGTH OF MATERIALS.
MLA	Sun, Z. J.,et al."Thermo-Fluid-Solid Coupling Analysis on the Hot Water Pipeline in the Nuclear Reactor Water System".STRENGTH OF MATERIALS (2024).