期刊文献+

小通道振荡导致密度锁失效研究

Research on Invalidation of Density Lock by Oscillation in Small Channels
下载PDF
导出
摘要 对密度锁内小通道振荡现象进行实验研究,发现密度锁失效是由于某一小通道内的分层界面在振荡过程中超出栅格,从而在小通道间形成循环所致。通过理论分析,提出3种解决方法:改变通道管径、减小通道间压差和扰动均匀化,以此为依据设计密度锁结构并进行实验进行验证。结果表明:改变通道管径只有在振荡界面通过管径变化处时才起作用;减小通道间压差的方法则需增加密度锁长度;扰动均匀化是最佳方法,可有效地减弱振荡幅度。 Experiment study on small channels oscillation in density lock is carried out.The invalidation of density lock is due to the stratified interface of one small channel going beyond during the process of oscil-lation,and a circulation is formed among small channels.Three solutions are proposed through the theoretical analysis: variability of diameter channels,reduction of pressure among channels and disturbance of homog-enization.According to these solutions,the density lock structures are designed and verified through experi-ment.The result shows that the variability of diameter channels would effect only when oscillation passed;the way of reducing pressure among channels would increase the length of density lock and the disturbance of homogenization could reduce the oscillation effectively.
出处 《核动力工程》 EI CAS CSCD 北大核心 2010年第6期75-79,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 振荡 失效 结构 Density lock Oscillation Invalidation Structure
  • 相关文献

参考文献7

二级参考文献18

  • 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. 被引量:1
  • 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. 被引量:1
  • 3MIZUNO T, ITO T, OHTA K. The inherentlysafe fluidized-bed boiling water reactor concept [J]. Annals of Nuclear Energy, 1990, 17 (9) : 487-492. 被引量:1
  • 4BABALA D. Pressurized water reactor inherent core protection by primary system thermohydraulies[J]. Nuclear Science and Engineering, 1985, 90(3) : 400-410. 被引量:1
  • 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. 被引量:1
  • 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. 被引量:1
  • 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. 被引量:1
  • 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. 被引量:1
  • 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. 被引量:1
  • 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. 被引量:1

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