期刊文献+

热管技术及性能分析程序研究

Research on Heat Pipe Technology and Performance Analysis Code
下载PDF
导出
摘要 作为一种高效的热传输手段,热管具备可靠性高、传热温差小、无需外力驱动等特点,因此在航天航空、核工程等领域得到广泛研究和应用。为更好地应用热管技术开展新型反应堆的设计和研发,掌握热管性能分析的理论方法和软件工具,本文开展了热管技术及相关程序的开发。对热管的结构和工作原理、种类、工作特性等进行了分析,研究了热管分析的基本理论和各种传热极限的计算模型。在此基础上开发了热管性能分析程序HEPAC,其具备各类热管的传热特性分析及传热极限计算能力,通过与相关实验数据的对比分析,验证了程序的正确性。相关程序开发为各种热管式反应堆的设计分析提供了重要工具。 As an efficient means for heat transfer,heat pipes have the characteristics of high reliability,low temperature difference and no need of external driving,so they have been widely studied and applied in aerospace,nuclear engineering and other fields.In order to apply this technology to the design and development of new type reactors,the theoretical method and performance analysis code of heat pipe were researched.The structure,working mechanism,type and performance characteristic of heat pipe were analyzed.The heat pipe theory and calculation models of heat transfer limits were studied.On this basis,the heat pipe performance analysis code HEPAC was developed,which had the ability to analyze the heat transfer characteristics and calculate the heat transfer limits for various types of heat pipes.The HEPAC code was tested and verified by comparing with the relevant experimental data.The code development provides an important tool for the design and analysis of various types of heat pipe reactors.
作者 陈其昌 CHEN Qichang(Shanghai Nuclear Engineering Research&Design Institute Co.,Ltd.,Shanghai 200233,China)
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2020年第7期1176-1184,共9页 Atomic Energy Science and Technology
基金 国家重点研发计划“核安全与先进核能技术”重点专项资助(2019YFB1901102)。
关键词 热管 反应堆 性能分析 HEPAC程序 heat pipe reactor performance analysis HEPAC code
  • 相关文献

参考文献8

二级参考文献42

  • 1王零森,方寅初,尹邦跃.碳化硼(B_4C)热导率和膨胀系数及其影响因素分析[J].粉末冶金材料科学与工程,2002,7(1):1-5. 被引量:2
  • 2杨启法,卢浩琳.空间核反应堆电源研究和应用[J].航天器工程,1995,4(4):11-20. 被引量:22
  • 3袁红球,胡大璞.高次端点浮动法—解点堆中子动力学方程[J].核动力工程,1995,16(2):124-128. 被引量:16
  • 4EI-Genk, M.S. and Tournier, J:M. , "Conceptual Design of HP-STMCs Space Reactor Power System for 110 kWe, 10-Year Missions [C]. Proceedings of the Space Technology and Applications International Forum (STAIF-2004), edited by M.S. EI-Genk, American Institute of Physics, Melville, NY, 2004a.
  • 5MOHAMED S. EL-GENK and JEAN-MICHEL E TOURNIER. " SAIRS "- SCALABLE AMTEC INTEGRATED REACTOR SPACE POWER SYSTEM [J]. Progress in Nuclear Energy, 2004,45(1):25-69.
  • 6Judith F Briesmeister, Editor. MCNP-A General Monte Carlo N-particle Transport Code. Version 4B [M].Los Alamos National Laboratory,LA-12625-M.
  • 7E1-Genk, M.S. and Tournier, J:M., Mechanically Alloyed-Oxide Dispersion Strengthened Steels for Use in Space Nuclear Power Systems[C]. in these Proceedings of the Space Technology and Applications International Forum ( STAIF-2004 ), edited by M. S, EI-Genk, American Institute of Physics, Melville, NY, 2004b.
  • 8King J. C. and E1-Genk M. S. (2004), A Methodology for the Neutronics Design of Space Nuclear Reactors [ C ]. Proc. Space Technology and Applications International Forum (STAIF-2004), M. S. E1-Genk, Ed., AIP-CP-699, American Institute of Physics, Melville, NY, 2004, pp. 319-329.
  • 9Stacey, W. M. , 2001. Nuclear Reactor Physics[M]. Wiley and Sons. Mew York, NY. 140.
  • 10Hatton, S.A., E1-Genk, M.S., Sectored compact space reactor (SCoRe) concepts with a supplementary lunar regolith reflector [J ]. Journal of Progress in Nuclear Energy 51(2009),93-108.

共引文献48

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