期刊文献+

密度锁内流体分层界面下移情况的相关研究

Research on Movement of Fluid Stratification Interface in Density Lock
下载PDF
导出
摘要 分析了密度锁内流体分层界面形成的原因,建立了一个简单的力学模型解释界面下移的原理,通过实验数据验证了这一原理;并通过实验验证了栅格形状、栅格尺寸、扰动大小和温差因素对界面下移速度的影响。结果表明:四种因素中栅格尺寸和温差对界面下移速度有影响,栅格小通道截面面积越小,界面下移越慢;温差越大,界面下移越慢。 The cause for the formation of fluid stratification interface was analyzed,and a simple mechanical model was founded to interpret the principle of interface movement. The effects of the grid shape and size,the disturbance magnitude and temperature difference on the interface removal speed was validated experimentally. The results indicated that only the grid size and temperature difference had effect on the interface movement speed. The smaller the channel sectional area was and the larger temperature difference was,the more slowly the interface moved.
出处 《核动力工程》 EI CAS CSCD 北大核心 2010年第S1期39-43,共5页 Nuclear Power Engineering
基金 国家自然科学基金资助项目(50776022)
关键词 界面形成 界面下移 栅格尺寸 温差 Interface formation,Interface movement,Size of the grid,Temperature difference
  • 相关文献

参考文献8

  • 1谷海峰,阎昌琪,王升飞.密度锁内稳态分层特性的实验研究[J].原子能科学技术,2009,43(1):51-55. 被引量:5
  • 2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
  • 3Griboriev O G,Leonchyk M P.IRIS:Minimizing Internal Energy Accumulated in the Primary Circuit of an Integral PIUS Type PWR with Natural Circulation. Procee-dings of a Technical Committee Meeting . 1997
  • 4Takahiro Ito,Tetsuya Kamihama.Thermal-Hydraulic Experiments of an Advanced PIUS-type Reactor. International Conference on Nuclear Engineering . 1996
  • 5Babala.Pressurized water reactor Inherent Core Protection by Primary System Thermohydraulics. Nuclear Science Journal . 1985
  • 6Takayuki Mizuno,Tatsuya ito.The inherently-safe fluidized-bed boiling water reactor concept. Ann.nucl.Energy . 1990
  • 7L.Cinotti,F.L.Rizzo.The inherently safe immersed system (ISIS) reactor. Nuclear Engineer The . 1993
  • 8B.Richard Gebart,Ingemar A.A.Lindblad,R Henrik Alfrredsson,Arne V. Johansson.How to suppress transport across a density interface. Stratified Flows . 1990

二级参考文献13

  • 1JUHN P E, KUPITZ J, CLEVELAND J, et al. IAEA activities on passive safety systems and overview of international development[J]. Nucl Eng Des, 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.
  • 3MIZUNO T, ITO T, OHTA K. The inherentlysafe fluidized-bed boiling water reactor concept [J]. Annals of Nuclear Energy, 1990, 17 (9) : 487-492.
  • 4BABALA D. Pressurized water reactor inherent core protection by primary system thermohydraulies[J]. Nuclear Science and Engineering, 1985, 90(3) : 400-410.
  • 5PIND C, FREDELL J. Summary of theoretical analyses and experimental verification of PlUS density lock development program [C]//IAEA Technical Committee Meeting (TCM) on Progress in Development and Design Aspects of Advaneed Water-Cooled Reactors in Rome. Vienna:IAEA, 1991: 213-219.
  • 6TASAKA K, IMAI S, MASAOKA H, et al. Feedback control of a primary pump for safe and stable operation of a PIUS-type reactor[J]. Nucl Eng Des, 1993, 144(2): 345-352.
  • 7HAGA K, TASAKA K, KUKITA Y. The simulation test to start up the PlUS-type reactor from Isothermal fluid condition[J]. J Nucl Sci Technol, 1995, 32(9): 846-854.
  • 8ITO T, KAMIHAMA T, NOBUHARA F, et al. Thermal-hydraulic experiments of an advanced PIUS-type reactor [C]//International Conference on Nuclear Engineering. New York: [s.n.], 1996: 163-170.
  • 9Juhn 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.
  • 10Mehedinteanu 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.

共引文献6

相关作者

内容加载中请稍等...

相关机构

内容加载中请稍等...

相关主题

内容加载中请稍等...

浏览历史

内容加载中请稍等...
;
使用帮助 返回顶部