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自然循环系统摇摆条件下棒束通道内传热特性研究 被引量:1

Flow Heat Transfer Characteristic in Rod Bundle Channel in Natural Circulation System for Rolling Condition
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摘要 棒束燃料元件子通道间流体存在搅混与横向二次流,流动及阻力特性相较矩形通道、圆管等简单通道更为复杂。核动力舰船、船舶、小型浮动核电站等会受到海浪影响,经常处于倾斜、摇摆、垂荡等瞬变运动下。目前的相关研究多集中在低压工况的研究领域,高温高压自然循环运动条件下的研究较少。本文采用实验研究方法,对自然循环系统摇摆条件下棒束通道内流动传热特性进行了研究,获得了过冷沸腾和饱和沸腾两种条件下摇摆角度和摇摆周期对棒束壁面温度变化和传热系数的影响,并获得了摇摆周期内棒束通道内的传热系数计算关系式。结果表明,饱和沸腾传热系数变化比过冷沸腾的剧烈;在本文实验工况范围内,棒表面传热系数波动幅值随着摇摆幅度的增大而增大;摇摆条件下棒束通道过冷沸腾和饱和沸腾工况时均传热系数基本不变。 There is mixing and second flow in sub-channels of the rod bundle.The flow and heat transfer characteristics in rod bundle are more complex than those in rectangular channel and round pipes.Nuclear power ships and floating nuclear power plants are constantly affected by sea waves and hence are under rolling conditions.Literature review shows that the rod bundle channel experiments are mainly under low pressure,while there are only a few studies on the high pressure flow heat transfer characteristics in rod bundle channels under natural circulation conditions.This research conducted many experiments and studied the flow heat transfer characteristics in the rod bundle channel under rolling motion.The main system included test section,condenser,pressurizer,controlling valves,flow meter,pre-heater et al.Natural circulation can be generated in the experimental system through the arrangement of the location of hot source and cold source.The test section is a 3×3 rod bundle channel and the heating length of the rod bundle channel is 0.8 m.Two thermocouples were installed on each cross section in each channel to measure wall temperatures and the pressure drop between each point was measured.The effects of rolling amplitude and rolling period on the rod bundle wall temperatures and heat transfer coefficient were obtained for subcooled boiling and saturated boiling.The rod bundle channel heat transfer coefficient relations were calculated.The experimental results show that during the rolling process,the system flow rate will fluctuate and result in the periodical fluctuation of the subcooled boiling void fraction distribution and fluid temperature fluctuation,and then lead to the periodical change of the heat transfer coefficients of the rod bundle.As the rolling amplitude increase,the fluctuation of the heat transfer coefficient also increases.The rolling period has a small effect on the subcooled boiling heat transfer coefficient.As the rolling period increases,the influence of the rolling motion on the flow in the rod bundle is weakened,and the fluctuation of the heat transfer coefficient is smaller.The heat transfer coefficients for saturated boiling fluctuate more strongly than the coefficients for subcooled boiling.The results show that for the experimental conditions,as rolling amplitude increases,the saturated boiling rod bundle channel heat transfer coefficients will increase.The average heat transfer coefficient during rolling motion is almost the same with the heat transfer coefficient at steady conditions for both saturated boiling and subcooled boiling,which means rolling has relatively small effect on the overall heat transfer despite of the periodical change of the transient heat transfer coefficient during the rolling process.
作者 毕景良 谢峰 黄彦平 徐建军 袁德文 昝元锋 BI Jingliang;XIE Feng;HUANG Yanping;XU Jianjun;YUAN Dewen;ZAN Yuanfeng(CNNC Key Laboratory on Nuclear Reactor Thermal Hydraulics Technology,Nuclear Power Institute of China,Chengdu 610041,China)
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2022年第8期1575-1583,共9页 Atomic Energy Science and Technology
基金 国家自然科学基金(12005217) 中国科协青年人才托举工程(2019QNRC001) 先进核能系统热工安全四川省青年科技创新研究团队(2019JDTD0018)。
关键词 棒束通道 两相流 摇摆运动 自然循环 流动传热 rod bundle channel two-phase flow rolling motion natural circulation flow heat transfer
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