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	Design and tests of a double-tube bundle heat exchanger for an integrated nuclear reactor
	Chen Minghui ; Li Rizhu ; He Xiaoyan ; Liu Junqiang
	2010-05-10 ; 2010-05-10
关键词	Practical/ fission reactor cooling fission reactor design heat exchangers heat transfer/ double-tube bundle heat exchanger integrated nuclear reactor analytical model thermal-hydraulic design structural optimization surface heat flows heat transfer coefficient power density natural circulation forced circulation 19-module heat exchanger thermal-hydraulic experiments/ A2843B Cooling and heat recovery in fission reactors A2841D Fission reactor design A4725Q Convection and heat transfer B8220B Nuclear reactors
中文摘要	An analytical model of thermal-hydraulic design and structural optimization was developed for a double-tube bundle heat exchanger of an integrated nuclear reactor. The method considered the surface heat flows, the heat transfer coefficient, the power density, and other characteristics of the heat exchanger for natural circulation or forced circulation. A 19-module heat exchanger was designed based on the conclusion that center distances between 15.8 mm and 16.4 mm are better for natural circulation. Thermal-hydraulic experiments show that the error of the predicted heat transfer coefficients is less than 5%, while the error of the pressure drop is less than 10%.
语种	中文 ; 中文
出版者	Tsinghua Univ. Press ; China
内容类型	期刊论文
源URL	[http://hdl.handle.net/123456789/23166]
专题	清华大学
推荐引用方式 GB/T 7714	Chen Minghui,Li Rizhu,He Xiaoyan,et al. Design and tests of a double-tube bundle heat exchanger for an integrated nuclear reactor[J],2010, 2010.
APA	Chen Minghui,Li Rizhu,He Xiaoyan,&Liu Junqiang.(2010).Design and tests of a double-tube bundle heat exchanger for an integrated nuclear reactor..
MLA	Chen Minghui,et al."Design and tests of a double-tube bundle heat exchanger for an integrated nuclear reactor".(2010).

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