| 注册
首页|期刊导航|原子能科学技术|竖直圆管内超临界压力氟利昂传热试验研究

竖直圆管内超临界压力氟利昂传热试验研究

张思宇 程旭 顾汉洋

原子能科学技术2015,Vol.49Issue(12):2150-2156,7.
原子能科学技术2015,Vol.49Issue(12):2150-2156,7.DOI:10.7538/yzk.2015.49.12.2150

竖直圆管内超临界压力氟利昂传热试验研究

Experimental Study on Heat Transfer of Supercritical Freon Flowing in Vertical Tube

张思宇 1程旭 2顾汉洋1

作者信息

  • 1. 上海交通大学核科学与工程学院,上海 200240
  • 2. 环境保护部核与辐射安全中心,北京 100082
  • 折叠

摘要

Abstract

The in-depth study on heat transfer characteristics of fluids under supercriti-cal pressure is crucial to the core design of supercritical water-cooled reactor (SCWR) . Heat transfer experiments of supercritical Freon R134a flowing upward in a circular tube were carried out with pressure of 4.3-4.7 MPa ,mass flux of 600-2 500 kg/(m2 · s) and heat flux of 20-180 kW/m2 .The heat transfer coefficient is close to the value calculated by Dittus-Boelter correlation in the region far from the pseudo-critical temperature . However ,it is much smaller than the value calculated by Dittus-Boelter correlation with larger heat flux in the region approaching pseudo-critical temperature .The heat transfer deterioration occurs at the condition of small mass flux and large heat flux .It is show n that the heat transfer coefficient is of significant relevance with both acceleration effect dimensionless number and buoyancy dimensionless number .The correlation of onset of heat transfer deterioration is proposed based on experimental data .The heat transfer coefficient calculated by Bishop correlation show s a small standard error but an overall overestimate .The value calculated by Jackson correlation shows a small average error but a larger standard error .

关键词

超临界传热/换热系数/传热关系式/无量纲数/传热恶化

Key words

supercritical heat transfer/heat transfer coefficient/heat transfer correla-tion/dimensionless number/heat transfer deterioration

分类

能源科技

引用本文复制引用

张思宇,程旭,顾汉洋..竖直圆管内超临界压力氟利昂传热试验研究[J].原子能科学技术,2015,49(12):2150-2156,7.

基金项目

国家自然科学基金资助项目(51206106 ) (51206106 )

原子能科学技术

OA北大核心CSCDCSTPCD

1000-6931

访问量0
|
下载量0
段落导航相关论文