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环形通道内钠流动起始沸腾壁面过热度实验研究
引用本文:仇子铖,秋穗正,巫英伟,苏光辉,田文喜.环形通道内钠流动起始沸腾壁面过热度实验研究[J].原子能科学技术,2014,48(3):422-428.
作者姓名:仇子铖  秋穗正  巫英伟  苏光辉  田文喜
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.西安交通大学 核科学与技术系,陕西 西安710049
基金项目:核能开发科研技术研究项目资助(HK·KD1003-4)
摘    要:对环形通道内金属钠起始沸腾壁面过热度进行实验研究。实验段长800 mm,环形通道外径10 mm,内径6 mm。电加热元件最高热流密度为846 kW/m2,进口过冷度为63.1~287.8 ℃,质量流量为7.2~122.0 kg/h,系统压力为0.85~28.79 kPa。实验结果表明,起始沸腾壁面过热度随热流密度和进口过冷度的增加而升高,随质量流量和系统压力的增加而降低。拟合得到了关于起始沸腾壁面过热度的半经验关系式,关系式计算结果与实验数据符合良好。

关 键 词:液态金属钠    起始沸腾壁面过热度    环形通道

Experimental Study on Incipient Boiling Wall Superheat of Sodium Flowing in Annulus
QIU Zi-cheng,QIU Sui-zheng,WU Ying-wei,SU Guang-hui,TIAN Wen-xi.Experimental Study on Incipient Boiling Wall Superheat of Sodium Flowing in Annulus[J].Atomic Energy Science and Technology,2014,48(3):422-428.
Authors:QIU Zi-cheng  QIU Sui-zheng  WU Ying-wei  SU Guang-hui  TIAN Wen-xi
Affiliation:1.State Key Laboratory on Power Engineering and Multiphase Flow, Xi’an Jiaotong University, Xi’an 710049, China;2.Department of Nuclear Science and Technology, Xi’an Jiaotong University, Xi’an 710049, China
Abstract:The incipient boiling wall superheat of sodium flowing in annulus was experimentally investigated. The annulus is the length of 800 mm, the inside diameter of 6 mm and the outside diameter of 10 mm. Experimental conditions are that the heat flux is 128-846 kW/m2, the inlet subcooling is 63.1-287.8 ℃, the mass flow rate is 7.2-122.0 kg/h and the system pressure is 0.85-28.79 kPa. The experimental results indicate that the incipient boiling wall superheat increases with the heat flux and the inlet subcooling, and reduces with the increase of the mass flow rate and the system pressure. A semi-empirical correlation was gained from experimental results. The predicting results agree well with experimental data.
Keywords:liquid sodium  incipient boiling wall superheat  annulus
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