圆管内铅铋共晶传热预测的新关联

Zhengquan Wang, Q. Wen, Shijia Xu
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摘要

液态铅或铅铋共晶具有良好的热物理性能、中子性能和自然循环能力。它是铅基快堆(LFR)的首选冷却材料。然而,在铅基快堆的热工设计和安全分析规范制定过程中,存在着一个基本问题,即液态铅和铅铋共晶的传热特性及其定量关系。现有的关系式大多是用特定条件下的实验数据拟合的,在较宽的参数范围内适用性较差,影响了热工设计和安全分析结果的准确性。因此,有必要建立实验数据库和相关数据库,以便在更大的参数范围内获得更准确的液态铅铋共晶传热相关性。本文回顾了近70年来关于液态铅和铅铋共晶传热特性的典型理论和实验研究,并基于已发表文献的传热实验数据建立了一个实验数据库,该数据库的数据点包括广泛的热力学参数内径范围为9.00至16.56 mm,温度范围为250.0至412.80°C,热流从20.0至12900.0 kW/m2,质量通量从0至12.0 kg/m2。在此基础上,对液态铅和铅铋共晶的典型传热关系式进行了评价和分析,建立了一个新的传热关系式,其适用范围为100 < Pe < 5800。结果表明,新相关性的平均绝对相对误差为16.64%,平均相对误差为0.74%,标准差为4.37%,总数据点误差在±20%以内的误差为65.27%。因此,本文提出的传热相关性可以很好地预测管内高温液态铅或铅铋共晶的传热系数。
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A New Correlation for Predictions of Heat Transfer of Lead-Bismuth Eutectic in Circular Tubes
Liquid lead or lead-bismuth eutectic has good thermal physical properties, neutron performances, and natural circulation capacity. It is the first choice of coolant material for the lead-based fast reactor (LFR). However, there is a fundamental problem, heat-transfer characteristics and quantitative relationship of liquid lead and lead-bismuth eutectic, to be solved in the process of thermal-hydraulic design and safety analysis code development of lead-based fast reactor. The existing correlations are mostly fitted by the experimental data under specific conditions and the applicability is poor in a wide range of parameters, which affects the accuracy of thermal-hydraulic design and safety analysis results. Therefore, it is a necessity to establish experimental databases and correlation databases to obtain a more accurate heat transfer correlation of liquid lead and bismuth eutectics within a wider range of parameters. This paper reviews the typical theoretical and experimental studies on the heat transfer characteristics of liquid lead and lead-bismuth eutectics in the recent 70 years, and an experimental database based on the heat transfer experimental data in the published literature is established, which data points include a wide range of thermodynamic parameters — inner diameter ranging from 9.00 to 16.56 mm, temperature from 250.0 to 412.80 °C, heat fluxes from 20.0 to 12900.0 kW/m2, and mass fluxes from 0 to 12.0 kg/m2s. Based on the database, the typical heat transfer correlations of liquid lead and lead-bismuth eutectics are evaluated and analyzed, and a new heat transfer correlation is developed, its suitable range is 100 < Pe < 5800. The results show that the mean absolute relative error of the new correlation is 16.64%, the average relative error is 0.74%, the standard deviation is 4.37%, and the error of 65.27% of the total data points is within ± 20%. Therefore, the heat-transfer correlation proposed in this study can well predict the heat-transfer coefficient of high-temperature liquid lead or lead-bismuth eutectic in the tube.
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