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作 者:宋明亮[1] 马建[1,2] 黄彦平[2] 张雨[1] 林震霞[1] Song Mingliang;Ma Jian;Huang Yanping;Zhang Yu;Lin Zhenxia(Technology Development and Support Division Nuclear Service,Nuclear Power Institute of China,Chengdu,610213,China;CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China,Chengdu,610213,China)
机构地区:[1]中国核动力研究设计院技术开发与支持处,成都610213 [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,成都610213
出 处:《核动力工程》2021年第2期88-92,共5页Nuclear Power Engineering
摘 要:以垂直向上窄间隙矩形通道为研究对象,开展了恒热流密度加热条件下的单相流动特性实验研究。根据测量的温度、流量、压降和热流密度,获得一定工况范围内层流、过渡流和湍流流动的非等温摩擦系数实验数据,并基于这些实验数据对现有的预测关系式进行了对比评价。结果表明,由Kays和Clark提出的层流等温摩擦系数关系式以及由Blasius、Techo、Moody提出的湍流等温摩擦系数关系式的预测结果均与相应的实验结果具有较好的一致性。In this paper, a vertical upward narrow gap rectangular channel is taken as the research object, and the experimental study of single-phase flow characteristics under constant heat flux density of heating conditions is carried out. According to the measured temperature, flow rate, pressure drop and heat flux density, the experimental data of non-isothermal friction factors including laminar, transitional and turbulent flows in a certain range of working conditions are obtained, and the existing empirical correlations are compared and evaluated with the experimental data. The result shows that the predictions of laminar flow friction factor proposed by Kays and Clark and the predictions of turbulent flow friction factors proposed by Blasius, Techo and Moody respectively have a good agreement with the relevant experimental data.
分 类 号:TL334[核科学技术—核技术及应用]
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