期刊文献+

影响密度锁内热-冷流体分界面因素的实验研究

Experimental study on the factors affecting the interface between hot and cold fluid in the density lock
下载PDF
导出
摘要 对3种不同管径的实验管段进行实验,研究稳态工况下扰动和热-冷流体温度差对密度锁内热-冷流体分界面位置的影响.结果表明,随着扰动的增大,扰动产生的湍流作用逐渐增强,从而使稳定的分界面向下移动;而温度差的增大,使热流体向冷流体的传热能力增强,导致分界面的位置下降.另外,对不同管径的实验管段的研究表明,在密度锁内布置一个蜂窝结构可有效地抑制扰动作用,使其内部的分界面更稳定. Under steady state condition, an experimental study on the influence of disturbance and temperature difference between hot and cold fluid on the location of interface was done in three different experimental pipes. The results showed that the effect of turbulence caused by disturbance increased with the enhancement of disturbance so that the location of stable interface between hot and cold liquid declined. And the heat transfer from hot liquid to cold liquid increased with the raise of temperature difference, which resulted in decline of the interface. In addition, the results of study on different experimental pipes indicated that a honeycomb structure in the density lock could efficiently curb the disturbance, which benefited the stability of the interface.
出处 《应用科技》 CAS 2009年第4期57-60,共4页 Applied Science and Technology
基金 国家自然科学基金资助项目(50776022)
关键词 密度锁 分界面 温度场 影响因素 density lock interface temperature field influencing factors
  • 相关文献

参考文献4

  • 1吕襄波,阎昌琪,孙立成.密度锁在反应堆非能动安全中的作用分析[J].核动力工程,2005,26(6):605-608. 被引量:5
  • 2PIND C. The Secure heating reactor[ J]. Nuclear Technology, 1987,79 : 175-185.
  • 3PEDERSEN T. PlUS-status and perspectives[ J]. Nuclear Engineering and Design, 1992,136 : 167-177.
  • 4MEHEDINTEANU S. An application of the new way to prevent core melting in pressure tube reactor ( CANDU type) [J]. Annals of Nuclear Energy, 2001, 28:79-88.

二级参考文献7

  • 1Juhn P E, Kupitz J, Cleveland J. IAEA Activities on Passive Safety Systems and Overview of International Development [J]. Nuclear Engineering and Design, 2000, 201(48): 49 - 54.
  • 2崔广余译.当代压水堆核电站发展新趋势(第一版)[M].北京:机械工业出版社,1997.259-268.
  • 3Mehedinteanu S. An Application of the New Way to Prevent Core Melting in Pressure Tube Reactor (CONDU type) [J]. Annals of Nuclear Energy, 2001, 28: 79 - 88.
  • 4Hiroaki Wakabayashi. Response of the ISER for a Beyond-Design-Basis Hypothetical Accident [J]. Nuclear Engineering and design. 1995, 158:135 - 147.
  • 5Takayuki Mizuno, Tatsuya Ito. The Inherent-Safe Fluid-ized-Bed Boiling Water Reactor Concept [J]. Ann Nuclear Energy. 1990, 17(9): 487 - 492.
  • 6Takahiro Ito. Thermal-Hydraulic Experiments of an Advanced PIUS-Type Reactor [C]. International Conference on Nuclear Engineering. Louisiana USA, Marchl0-14.ASME, Vol.2, 1996, 163 - 170.
  • 7Pind, C, Fredell, J. Summary of Theoretical Analyses and Experimental Verification of PIUS Density Lock Development Program [C]. IAEA Technical Committee Meeting (TCM) on Progress in Development and Design Aspects of Advanced Water-cooled Reactors, Rome, IAEA ref. 13-tc-633.14 September 1991, 213 - 219.

共引文献4

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