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环形通道内液态金属钠沸腾两相传热特性实验研究
引用本文:仇子铖,兰治科,秋穗正,谢旭,鲁晓东,孙都成.环形通道内液态金属钠沸腾两相传热特性实验研究[J].原子能科学技术,2017,51(3):418-424.
作者姓名:仇子铖  兰治科  秋穗正  谢旭  鲁晓东  孙都成
作者单位:1.西安交通大学 动力工程多相流国家重点实验室,陕西 西安710049;2.中国核动力研究设计院 中核核反应堆热工水力技术重点实验室,四川 成都610041
摘    要:对环形通道内液态金属钠沸腾两相流动特性进行了实验研究。实验中,系统压力为3.6~110.0kPa,热流密度为11~600kW·m~(-2),流速为0.02~0.45m·s~(-1)。实验结果表明,液态金属钠沸腾传热系数与壁面热流密度和系统压力有强烈关系,而与入口过冷度和质量流速无关。在本文实验数据基础上,拟合得到了计算液态金属钠沸腾两相传热系数的关系式,通过与各组实验数据间的比较,证明本文关系式适用于计算环形通道内液态金属钠沸腾两相传热系数。

关 键 词:液态金属钠    环形通道    沸腾    传热系数

Experimental Research on Heat Transfer Characteristics of Boiling Two-phase Liquid Sodium in Annuli
QIU Zi-cheng,LAN Zhi-ke,QIU Sui-zheng,XIE Xu,LU Xiao-dong,SUN Du-cheng.Experimental Research on Heat Transfer Characteristics of Boiling Two-phase Liquid Sodium in Annuli[J].Atomic Energy Science and Technology,2017,51(3):418-424.
Authors:QIU Zi-cheng  LAN Zhi-ke  QIU Sui-zheng  XIE Xu  LU Xiao-dong  SUN Du-cheng
Affiliation:1.State Key Laboratory of Multiphase Flow in Power Engineering, Xi’an Jiaotong University, Xi’an 710049, China;2.CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology, Nuclear Power Institute of China, Chengdu 610041, China
Abstract:Experimental research on the heat transfer characteristics of boiling two-phase sodium flowing in an annuli was done .Experimental conditions were system pressure from 3.6 to 110.0 kPa ,heat flux from 11 to 600 kW · m-2 and velocity from 0.02 to 0.45 m · s-1 .The experimental results show that the boiling heat transfer coefficient of sodium is affected significantly by the heat flux and system pressure instead of the inlet subcooling or mass flow rate .On the base of the experimental data ,a correlation of the heat transfer coefficient for boiling sodium was proposed .Applicability of this correla-tion to the liquid metal sodium boiling in an annuli was proved by comparing the correla-tion results to those experimental data .
Keywords:liquid sodium  annuli  boiling  heat transfer coefficient
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