首页> 外文会议>International topical meeting on nuclear reactor thermal hydraulics >EXPERIMENTAL AND NUMERICAL INVESTIGATION OF HEAT TRANSFER AND PRESSURE DROP IN STAGGERED ARRANGEMENT HELICALLY FINNED-TUBE BUNDLE
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EXPERIMENTAL AND NUMERICAL INVESTIGATION OF HEAT TRANSFER AND PRESSURE DROP IN STAGGERED ARRANGEMENT HELICALLY FINNED-TUBE BUNDLE

机译:交错排列螺旋形管束中传热和压降的实验和数值研究

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In a new pressurized water reactor nuclear power plant, the heat exchange tube bundle of the Moisture Separator Reheater (MSR) is a new designed staggered arrangement low helically finned-tube bundle. To investigation the thermal hydraulic characteristics of the Reheater part of MSR, the tube bundle test section was designed by using prototype tube and prototype arrangement of the new designed MSR. The experiment was carried out on the test section with steam cross-flowing outside the horizontal tube bundle, same conditions as MSR' operation designing , and electrical heating in the tubes simulating the condensation heat release of the two phase-flow inside. A lot of experimental data on heat transfer and pressure drop were obtained in a broad experiment parameters range of wall heat flux density and steam temperature, pressure and Reynolds number. Based on the present data, empirical average heat transfer correlation and friction factor correlation were proposed for the outside average heat transfer and pressure drop. Comparisons and analysis between these experimental results and some of other investigations were made. The conclusions of this experimental investigation were given. The results are very useful to the design of the heat exchange tube bundle in the MSR, and the validations of the new design. However, experimental studies cannot adequately reveal the detail of flow characteristics, and suitable correlations for this fin geometry are very rare. Thus, numerical simulations should be performed to make up for the deficiency. To perform a detail understanding of the heat transfer and pressure drop characteristics, a three-dimensional geometry was carefully constructed and a fine mesh was generated. The flow across the tubes was assumed to be a steady, incompressible turbulent flow. RNG based k-ε turbulence model was chosen in the simulation. Nusselt number and Euler number of a wide range of Reynolds numbers (based on the steam velocity through the minimum flow area) from 1 ×10~4 to 8×10~4 were calculated by the CFD software ANSYS Fluent. The numerical results were compared with experiment results of the same fin geometry and tube configuration. Also, local flow behavior and local temperature distribution were obtained to show the detail flow features and heat transfer. The velocity and temperature distribution near the fin surface were discussed
机译:在新的压水堆核电站中,水分分离器再热器(MSR)的热交换管束是一种新设计的交错排列的低螺旋翅片管束。为了研究MSR的再热器部分的热工水力特性,通过使用原型管和新设计的MSR的原型布置设计了管束测试段。实验是在测试段上进行的,蒸汽在水平管束的外部交叉流动,与MSR的操作设计相同,并且管中的电加热模拟了内部两相流的冷凝热释放。在壁热通量密度和蒸汽温度,压力和雷诺数的广泛实验参数范围内,获得了许多有关传热和压降的实验数据。基于目前的数据,提出了经验平均传热相关性和摩擦因数相关性的外部平均传热和压降。这些实验结果和其他一些研究之间进行了比较和分析。给出了该实验研究的结论。结果对于MSR中的热交换管束设计以及新设计的验证非常有用。但是,实验研究不能充分揭示出流动特性的细节,并且这种翅片几何形状的适当相关性非常罕见。因此,应进行数值模拟以弥补这一不足。为了详细了解传热和压降特性,精心构造了三维几何形状,并生成了细网格。假设流经管道的流量是稳定的,不可压缩的湍流。在仿真中选择了基于RNG的k-ε湍流模型。通过CFD软件ANSYS Fluent计算了从1×10〜4到8×10〜4的大范围雷诺数(基于通过最小流通面积的蒸汽速度)的Nusselt数和Euler数。将数值结果与相同翅片几何形状和管配置的实验结果进行了比较。此外,获得了局部流动行为和局部温度分布,以显示详细的流动特征和热传递。讨论了鳍片表面附近的速度和温度分布

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