期刊文献+

混凝土内部T型弯管流动换热数值模拟

Numerical simulation of flow heat transfer on T-junction embedded in concrete
下载PDF
导出
摘要 采用有限元方法计算了三通弯管的流场分布和换热效率。获得了T型弯管横截面的平均速度和Nu换热系数沿管程的分布曲线。数值结果表明,弯曲位置附近流场分布复杂,弯曲位置后水流量得到二次分配;分支管壁出现分离区和回流区,横截面出现二次流。Nu数在主管和分支管沿管长方向均出现衰减,且分支管衰减比率大于横向管。在数值分析混凝土结构温度场中,应注意弯管节点附近施加不同的换热系数。 A finite element method was developed to simulate the flow field distribution and the heat transfer efficiency of T-junction in concrete.The mean water velocity and Nusselt numbers on each section were obtained in this manuscript.Numerical results show that the flow field distribution was very complex and a new flow velocity was distributed in the junction position.A separation zone and recirculation zone appeared in the vicinity of bifurcation pipe wall,and a secondary flow appeared in the cross section.Nusselt number decreased gradually along the pipeline of the main pipe and the branch pipe,and the heat loss ratio in branch pipe is greater than main pipe.It suggested that the Nusselt heat transfer coefficient should be piecewise loaded the boundary conditions,when employ a numerical simulation method to analyze the concrete temperature field.
出处 《混凝土》 CAS CSCD 北大核心 2011年第6期57-59,共3页 Concrete
基金 中国地震局教师科研基金(20100106) 防灾科技学院防灾减灾青年科技基金(201002)
关键词 混凝土 有限元 T型弯管 换热系数 concrete finite element T-junction heat transfer coefficient
  • 相关文献

参考文献11

二级参考文献26

  • 1王解军,李辉,卢二侠.桥梁混凝土水管冷却温度场有限元分析[J].中南公路工程,2006,31(2):84-88. 被引量:14
  • 2廖振强.多分支管道若干流动现象和特性的探讨[J].气动实验与测量控制,1996,10(3):31-40. 被引量:6
  • 3王解军,卢二侠,李辉.大体积混凝土施工期的水化热温度场仿真分析[J].中外公路,2006,26(6):159-165. 被引量:25
  • 4赵英菊,王社良,康宁娟.ANSYS模拟大体积混凝土浇筑过程的参数分析[J].科技信息,2007(14):96-97. 被引量:25
  • 5[5]L Buffo-Lacarrière,A Sellier.Multiphasic Finite Element Modeling of Concrete Hydration[J].Cement and Concrete Research,2007,37(2):131-138.
  • 6[6]Jin Keun Kim,Kook Han Kim,Joo Kyoung Yang.Thermal Analysis of Hydration Heat in Concrete Structures with Pipe-Cooling System[J].Computers and Structures,2001,79(2):163-171.
  • 7[8]CHOI K S,YANG J K.Field Measurement of Hydration Heat and Application of Pipe Cooling System.Conf Kor Conc Inst,1994,(11):381-386.
  • 8Toshihira Muramatsu , Hisashi Ninokata. Investigation of Turbulence Modelling in Thermal Stratification Analysis[J]. Nuclear Engineering and Design, 1994, 150:81 - 93.
  • 9Validation of Fast Reactor Thermohydraulical and Thermohydraulic Codes [M]. IAEA, Vienna, 2002, IAEA-TECDOC- 1318.
  • 10Toshihira Muramatsu , Hisashi Ninokata. Evaluation of Stripping and Stratifaction in Nuclear Reactor (Report No.4)-Discussion for Algebraic Stress Turbulence Model[M], 1989.

共引文献63

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