期刊文献+

U型管式蒸汽发生器内改性壁面强化传热数值研究

Numerical Study on Heat Transfer Enhancement of Modified Wall in U-tube Steam Generator
原文传递
导出
摘要 为了达到较好的传热效果以及减少传热恶化造成管道破裂等事故的可能,本文基于改进的格子Boltzmann方法(LBM)相变传热模型,对蒸汽发生器U型传热管内工质的气泡动力学行为和壁面的传热性能进行了数值研究。结果表明:与纯亲水壁面相比,疏水区域促进气泡成核,混合润湿性壁面可以显著提高沸腾传热量。混合润湿性壁面可以提高临界热流密度(CHF),并延迟CHF点的出现,可以有效地减小传热恶化的可能。总体上,疏水点间距和个数决定气泡的生长状态,存在一个最佳疏水点设置可以获得最佳沸腾传热性能,选择合适的疏水点间距和个数可以得到理想的传热壁面。 In order to achieve better heat transfer effect and reduce the possibility of pipe rupture caused by heat transfer deterioration,based on the improved lattice Boltzmann method(LBM)phase transition heat transfer model,the bubble dynamics behavior and wall heat transfer performance of working medium in U-shaped heat transfer tube of steam generator were studied numerically.The results show that compared with the pure hydrophilic wall,the hydrophobic zone promotes bubble nucleation,and the wall with mixed wettability can significantly increase the boiling heat transfer.The wall with mixed wettability can increase the critical heat flux(CHF)and delay the occurrence of CHF point,which can effectively reduce the possibility of heat transfer deterioration.Generally speaking,the distance and number of hydrophobic points determine the growth state of bubbles,the best boiling heat transfer performance can be obtained if there is an optimal setting of hydrophobic points,and the ideal heat transfer wall can be obtained by selecting appropriate distance and number of hydrophobic points.
作者 袁俊杰 刘莉 顾汉洋 Yuan Junjie;Liu Li;Gu Hanyang(School of Nuclear Science and Engineering,Shanghai Jiao Tong University,Shanghai,200240,China)
出处 《核动力工程》 EI CAS CSCD 北大核心 2022年第S02期94-99,共6页 Nuclear Power Engineering
基金 国家自然科学基金(51906147) 上海市自然科学基金(21ZR1430900)
关键词 蒸汽发生器U型管 强化换热 格子Boltzmann方法(LBM) 混合润湿性 Steam generator U-tube Enhanced heat exchange Lattice Boltzmann method(LBM) Mixed wettability
作者简介 袁俊杰(1997—),男,硕士研究生,研究方向核科学与技术,E-mail:yuanjunjie@sjtu.edu.cn;通讯作者:刘莉,E-mail:liulide@sjtu.edu.cn
  • 相关文献

参考文献2

二级参考文献23

  • 1IAEA TECDOC-985. Accelerator driven systems : Energy generation and transmutation of nuclear waste. Status report [R].November 1997.
  • 2OECD/NEA, Accelerator-driven Systems (ADS) and Fast Reactors (FR) in Advanced Nuclear Fuel Cycles A Comparative Study [R].2002.
  • 3G. Bandini, et al. Thermal-hydraulics analysis of ELSY lead fast reactor with open square core option [J]. Nuclear Engineering and Design 241 (2011): 1165-1171.
  • 4A. Borgohain, et al. Natural circulation studies in a lead bismuth eutectic loop [J].Progress in Nuclear Energy 53 (2011) 308-319.
  • 5Tsuyoshi Okawa, et al. Design Study on Pb-208 Cooled CANDLE Burning Reactors toward Practical Application for Future Nuclear Energy Source [J]. Progress in Nuclear Energy 53 (2011) 886-890.
  • 6J. Wallenius, et al. A low power fast reactor cooled by natural circulation of LBE[R]. Proceedings of Global 2009, Paris, France, September 6-11,2009.
  • 7C. Rubhia, et a[. Conceptual Design of a Fast Neutron Operated High Power Energy Amplier [R].CERN/AT/ 95-44(et), (1995).
  • 8Luciano Cinotti,et al. The Pb Bi cooled XADS status of development[J]. Journal of Nuclear Materials 301, 2002: 8-14.
  • 9HamidAIT Abderrahim, et al. MYRRHA: A European Experimental ADS for R&D Applications Status at Mid-2005 and Prospective towards Implementation [J]. Journal of Nuclear Science and Technology, 2007,44 : 491-498.
  • 10Y. Kurata,et al. The accelerator driven system strategy in Japan [J].Journal of Nuclear Materials 301,2002: 1-7.

共引文献93

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