立式螺旋管汽液两相流沸腾传热恶化实验研究  

INVESTIGATION OF BOILING HEAT TRANSFER DETERIOEATION OF STEAM/LIQUID TWO-PHASE FLOW IN A VERTICAL HELICALLY COILED TUBE

作　　者：张文斌[1] 赵亮[1] 陈森林[1] 李德标[1] 郭烈锦[1] 

机构地区：[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

出　　处：《工程热物理学报》2009年第10期1673-1676,共4页Journal of Engineering Thermophysics

基　　金：国家自然科学基金重点项(No.50536020);优秀国家重点实验室研究项目(No.50823002);国家自然科学基金会创新研究群体科学基金项(No.50521604)

摘　　要：本文实验研究了低质量流速(500～800kg·m^(-2)·s^(-1))下的立式螺旋管临界热负荷,对沸腾传热恶化壁温特性和螺旋管临界热负荷影响因素进行分析。并同前人工作汇总,以流量,压力和临界干度为参数,建立了基于局部条件假设的立式螺旋管临界热负荷查询表(Look-Up-Table),共272个点.压力范围6.5～21 MPa,质量流速范围500～1800 kg·m^(-2)·s^(-1)。In this paper, we firstly experimentally investigate the deterioration of heat transfer in a helically coiled tubes at low mass velocity （500-800 kg·m^-2·s^-1）. We analyze the factors affecting of the deterioration of heat transfer coefficient correlations and the deterioration of heat transfer in helically coiled tubes. Based on previous work, a new look-up-table for critical heat flux has been set up, using mass flow rate, pressure and critical steam quality as parameters and based on the hypothesis of local conditions. In the range of mass flow rate of 500-800 kg·m^-2·s^-1 and pressure of 6.5-1 MPa, the LUT has 272 points.

关 键 词：临界热负荷 传热恶化 立式螺旋管 查询表 

分 类 号：O357[理学—流体力学]