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竖直管内两相流逆向流动特性研究 被引量:4

Investigation on Countercurrent Flow Characteristics in Vertical Tubes
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摘要 实验发现在竖直管内两相流逆向流动过程中,由于气体的入口条件不同,淹没开始点可能出现在气相的入口处,也可能出现在出口处。由于出现的位置不同,淹没开始点所对应的气、水之间的关系式也不一样。这一实验结果对进一步研究淹没开始的机理有重要意义。根据两相流的流动特性,分析了出现这种现象的原因,提出应采用不同的关系式计算这两种不同的淹没开始点。 : It is found in the experiment that for different air inlet the flooding may be occurred in air inlet or outlet in two- phase countercurrent flow.Since the positions of flooding are difference,the correlation between water flow rate and air flow rate for onset of flooding is difference.This result is of significant meaning for studying the mechanism of onset of flooding.The reason for this difference is analyzed based on two- phase flow characteristics.It is proposed that different correlation should be used to calculate the inlet flooding and outlet flooding.
出处 《核动力工程》 EI CAS CSCD 北大核心 2001年第1期15-18,共4页 Nuclear Power Engineering
关键词 两相流 逆向流动 淹没开始点 核反应堆 破口事故 安全分析 竖直管 : Two- phase flow; Ountercurrent flow; Flooding
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  • 1阎昌琪,孙福泰,孙仲宁.管径和气体入口条件对淹没过程的影响[J].核动力工程,1993,14(3):238-243. 被引量:8
  • 2彭云康.回流流动极限实验研究综述[J].核动力工程,1993,14(6):556-560. 被引量:10
  • 3阎昌琪,黄渭堂,王文祥,杜泽.竖管内淹没及其消失滞后问题的研究[J].核科学与工程,1994,14(1):34-41. 被引量:3
  • 4王金华,薄涵亮,姜胜耀,郑文祥.池式反应堆堆内流场数值模拟[J].原子能科学技术,2005,39(4):322-325. 被引量:6
  • 5LIU J Q, SUN B M, LI Z S, et al. Three Dimensional Numer- ical Simulation on Nuclear Reactor Interior Flow and Temper- ature Field of a 1000MW unit [J]. Research Journal of Ap- plied Sciences Engineering and Technology, 2013,6 ( I 1 ) : 2 019-2 026.
  • 6ISLAM M S, HINO R, HAGA K, et al. Experimental study on heat transfer augmentation for high heat flux removal in rib-roughened narrow channels [ J ]. Nuclear Science and Technology, 1998,35 (9) :671-678.
  • 7LIU J Q, SUN B M, BAIT. Numerical Simulation and Safety analysis on Flow Field of a 1000 MW Unit Nuclear reactor pressure vessel [ C ] //World Automation Congress. Puerto Vallart,Mexico,2012:1-4.
  • 8OKAY K. Design concept of once-through cycle super-criti- cal pressure light coolant cooled reactors[ C]//Proc. of SCR- 2000, Tokyo ,2000 : 1-22.
  • 9JEONGHY, HA K S, KWON Y M, et al. A dominant geomet-rical parameter affecting the turbulent mixing rate in rod bundles [ J ]. Heat and Mass Transfer, 2007,50 : 908-918.
  • 10LEE K B, JANG H C. A numerical prediction on the turbu- lent flow in closely spaced bare rod arrarys by a nonlinear k- E model [ J]. Nuclear Engineering and Design, 1997,172 : 351-357.

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