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密度锁内分层界面位置的实验研究及分析 被引量:1

Experimental Research and Analysis on Location of Stratified Interface in Density Lock
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摘要 建立了计算密度锁内流体分层界面位置的理论模型,比较了计算值与实验观察值,并分析了两者的区别,最后讨论了扰动速度和温差对界面位置的影响。结果表明:扰动速度增加,界面位置降低;温差变大,界面位置升高。在一定的温度和管径等条件下,分别拟合出界面位置与扰动速度及理查森数(Ri)的经验关系式。 A theoretical model is built to calculate the location of fluid stratified interface in density lock,the calculated values and experimental observations are compared and the difference between them are analyzed.The effect of disturbance velocity and temperature difference on the interface location is discussed,respectively.The result shows that the larger disturbance velocity responds to the lower interface location,and the higher temperature difference responds to the higher interface location.In condition of certain temperature and diameter,the experiential relationships among the interface location,disturbance velocity and Richardson number are fitted,respectively.
出处 《核动力工程》 EI CAS CSCD 北大核心 2010年第3期83-87,共5页 Nuclear Power Engineering
基金 国家自然科学基金资助项目(50776022)
关键词 密度锁 分层界面位置 扰动速度 理查森数 Density lock Location of stratified interface Disturbance velocity Richardson number
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参考文献8

  • 1Kare Hannerz. The PIUS Pressurized Water Reactor:Aspects of Plant Operation and Availablity[J]. Nuclear Salty, 1989, 82: 56-63P.
  • 2Takayuki Mizuno, Tatsuya ito.The Inherently-Safe Fluidized-Bed Boiling Water Reactor Concept[J]. Ann. nucl. Energy, 1990, 17(9): 487-492.
  • 3谷海峰,阎昌琪.密度锁内分层传热特性的初步探讨[J].核动力工程,2008,29(1):106-109. 被引量:6
  • 4Mario De Salve, Giovanni Del Tin, Bruno Panella. Temperature Field and Transport Phenomena across a Density interFace[C]. International Conference On Nuclear Engineering, Volumel, Part A, ASME 1996: 195-205.
  • 5王升飞.密度锁机理的实验研究[D].哈尔滨:哈尔滨工程大学,2007.
  • 6谷海峰.密度锁内流体分层特性的实验研究[D].哈尔滨:哈尔滨工程大学,2005.
  • 7Gebart B R, Lindblad I A A. How to Suppress Transport across a Density Interface[C]. London:Cambridge, 1986: 24-26.
  • 8Masahiro OSAKABEE, Toshisuke KUBO. Enerainment Behavior on Density Interface of Stratified Fluids[J]. JSME Internation Journal, 1992: 61-66.

二级参考文献5

  • 1Juhn PE, Kupitz J, Cleveland J, et al. IAEA Activities on Passive Safety Systems and Overview of International Development[J]. Nuclear Engineering and Design, 2000, 201(48): 49 - 54.
  • 2Mehedinteanu S. An Application of the New Way to Prevent Core Melting in Pressure Tube Reactors (CANDU type) [J]. Annals of Nuclear Energy, 2001, 28(1): 79 - 88.
  • 3Tasaka K, Imai S, Masaoka H, et al. Feedback Control of a Primary Pump for Safe and Stable Operation of a PIUS-Type Reactor[J]. Nuclear Engineering and Design, 1993, 144(2): 345 - 352.
  • 4Takahiro Ito, Tetsuya Kamihama, Fumiyoshi Nobuhara, et al. Thermal-Hydraulic Experiments of an Advanced PIUS-Type Reactor[C]. International Conference on Nuclear Engineering, Vol.2, ASME, 1996, 163-170.
  • 5Mario De Salve, Giovanni Del Tin, Bruno Panella. Temperature Field and Transport Phenomena Across a Density Interface[C]. International Conference on Nuclear Engineering. Volumel-partA, ASME 1996.

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