棒束子通道空泡份额及相界面浓度分布特性实验研究  

Experimental Study of Void Fraction and Interfacial Area Concentration Distribution Characteristics in Rod Bundle Subchannel

作　　者：任佳星 王若好 王方东 乔守旭 谭思超 田瑞峰 高璞珍 REN Jiaxing;WANG Ruohao;WANG Fangdong;QIAO Shouxu;TAN Sichao;TIAN Ruifeng;GAO Puzhen(Heilongjiang Provincial Key Laboratory of Nuclear Power System and Equipment,Harbin Engineering University,Harbin 150001,China)

机构地区：[1]哈尔滨工程大学黑龙江省核动力装置性能与设备重点实验室,黑龙江哈尔滨150001

出　　处：《原子能科学技术》2024年第S01期33-43,共11页Atomic Energy Science and Technology

基　　金：中核集团“青年英才”项目;国家自然科学基金(12275059)。

摘　　要：棒束通道相态分布特性对反应堆内传热传质及流动阻力具有重要影响。本文对5×5棒束通道空气水两相流开展实验研究,采用四头电导探针测量了子通道内部的空泡份额、相界面浓度、气泡直径、气泡速度等相界面参数的局部分布。结果表明,气泡受横向作用力的影响,在子通道内会形成两种典型分布,随液相流速升高和气相流速降低,轴峰分布逐渐转变为壁峰分布;不同类型子通道空泡分布不均匀,中心子通道受壁面影响较小,气泡数量最多,边通道和角通道几乎被液相占据;本实验工况下,现有的空泡份额和相界面浓度计算关系式预测性能良好,平均最小误差分别为±18.2%与±12.2%。The gas-liquid two-phase flow widely exists in nuclear energy,chemical industry,petroleum engineering,and other industrial production fields.Two-phase flow will occur in pressurized water reactors during normal operation and accident conditions.The distribution of void fraction and interfacial area concentration in rod bundle channels has an important influence on the flow resistance,heat transfer,critical heat flux,and power distribution of the reactor.The complex geometric structure of rod bundle channels brings a great challenge to the local experimental measurement of two-phase flow.As a result,the existing database of the interfacial structure parameters in rod bundle channels is still insufficient,which greatly affects the accuracy of two-phase flow modeling.To clarify the transformation mechanism of the phase distribution in rod bundle subchannels and provide a database for future modeling,an experimental study of air-water two-phase flow in a 5×5 rod bundle channel was carried out in this paper.The four-sensor conductivity probe was used to measure the distribution of local two-phase flow parameters(void fraction,interfacial area concentration,bubble diameter,and bubble velocity)across the test section at 36.5 hydraulic diameters.The results show that with the increase of liquid phase velocity and the decrease of gas phase velocity,the“axial peak”gradually changes to the“wall peak”under the influence of radial force.The transition boundary of phase distribution is obtained and has a relatively accurate classification effect.The non-uniform void fraction distribution over the cross-section is observed,bubbles tend to gather in the central subchannels which are less affected by the wall and have a higher mass velocity.For the overall cross-section,the decrease of liquid phase velocity and the increase of gas phase velocity exacerbate the non-uniformity of bubble distribution.In the experimental conditions of this paper,the established correlation of void fraction and interfacial area concentration

关 键 词：棒束通道 子通道 两相流 电导探针 相态分布 相界面浓度 

分 类 号：TL33[核科学技术—核技术及应用]