期刊文献+

蒸汽发生器U型管倒流现象的数值模拟和实验研究 被引量:2

Numerical Simulation and Experimental Study on Reverse Flow in U-tube of Steam Generator
在线阅读 下载PDF
导出
摘要 针对蒸汽发生器U型管倒流现象展开实验研究。基于实验数据,采用CFD方法对倒流进行模拟。结果表明:蒸汽发生器发生倒流后,进口腔室出现显著的温度分层,倒流现象降低了蒸汽发生器U型管的换热能力;发生倒流后,进出口腔室压降绝对值减小,正流管流速增大,流动阻力增大,倒流降低了系统的自然循环能力。 The experimental study on reverse flow in the inverted U-tube steam genera- tor was carried out. Based on experiment data, the experiment phenomenon was simula- ted by CFD method. The results show that reverse flow causes remarkable temperature stratified in inlet plenum and reduces the heat transfer capability of the steam generator U-tubes. The absolute value of pressure drop decreases in plenum when reverse flow occurs. The flow resistance increases while velocity of normal U-tubes increases, which has adverse influence on natural circulation.
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2017年第4期622-626,共5页 Atomic Energy Science and Technology
基金 国家自然科学基金资助项目(11502298 11402300) 中国核动力研究设计院核反应堆系统设计技术重点实验室基金资助项目(HDY-2015004) 哈尔滨工程大学核安全与仿真技术国防重点学科实验室专项科研基金资助项目(2015A041)
关键词 CFD 倒流 U型管 蒸汽发生器 CFD reverse flow U-tube steam generator
  • 相关文献

参考文献5

二级参考文献25

  • 1张勇,宋小明,黄伟.低流量下蒸汽发生器一次侧流量分配研究[J].核动力工程,2009,30(S1):56-59. 被引量:12
  • 2杨瑞昌,刘涛,钟勇,周立加.自然循环传热部件内单相水流动阻力的实验研究[J].核动力工程,2003,24(S2):75-78. 被引量:3
  • 3杨瑞昌,覃世伟,刘若雷.自然循环蒸汽发生器倒U型管内单相水流动及传热特性分析[J].工程热物理学报,2006,27(1):130-132. 被引量:11
  • 4王飞,卓文彬,肖泽军,陈炳德.立式倒U型管蒸汽发生器倒流现象及初步分析[J].原子能科学技术,2007,41(1):65-68. 被引量:19
  • 5Sanders J. Stability of Single-Phase Natural Circulation with Inverted U-Tube Steam Generators. Journal of Heat Transfer, 1988, 110:735-742.
  • 6Kukita Y, Nakamura H, Tasaka K, et al. Nonuniform Steam Generator U-Tube Flow Distribution During Natural Circulation Tests in ROSA-IV Large Scale Test Facility. Nuclear Science and Engineering, 1988, 99:289-298.
  • 7王飞,聂常华,黄彦平,等..自然循环静态特性研究,空泡物理和自然循环重点实验室年报..,,2003..130-135..
  • 8Jeong J J, Hwang M, Lee Y J, et al. Single-and TwoPhase Flow Characteristics in the Primary Side of a UTube Steam Generator. In: The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics. Seoul, Korea, 2003.
  • 9Stumpf H, Motly F, Schultz R, et al. Reverse Primary Side Flow in Steam Generators During Natural Circulation Cooling. American Society of Mechanical Engineering, Fluid Engineering Division(FED), 1987, 61:103-109.
  • 10臧系年,申世飞.核电厂系统及设备[M].北京:清华大学出版社,2003.

共引文献32

同被引文献20

引证文献2

二级引证文献1

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