Abstract The lead cooled fast reactor is considered as one of the most potential Generation IV nuclear systems due to the low working pressure, the appreciable neutron economy, and the considerable passive characteristics. Meanwhile, the lead bismuth eutectic (LBE) has the related advantages of lead with the weaker corrosiveness, which has been paid much attention by recent decades. Moreover, the sub-channel code is a necessary analysis tool for the reactor thermal-hydraulic design and safety analysis, which has been developed combined with the accumulation of LBE experimental data and the understanding of physical phenomena. In this study, a sub-channel code available for LBE was developed, and the corresponding geometric characterization method of typical sub-channels was described in detail, including the fuel assembly with wire spacer. As for this sub-channel code, the transversal thermal conduction through gap was taken into account. In addition, the physical properties, the heat transfer model, the flow resistance model and the turbulent mixing model were analyzed. Finally, the thermal-hydraulic experiments of LBE conducted on THEADES (THErmal-hydraulics and Ads DESign) were selected as the evaluation data of this sub-channel code, including 19 rods with grid spacer and wire spacer, and the calculated results were in good agreement with the experimental results.

中文翻译：

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可用于多种燃料组件结构的铅铋共晶快堆子通道代码开发

摘要 铅冷快堆由于其工作压力低、中子经济性显着、被动特性显着，被认为是最具潜力的第四代核系统之一。同时，铅铋共晶（LBE）具有铅腐蚀性较弱的相关优点，近几十年来受到广泛关注。此外，子通道代码是反应堆热工水力设计和安全分析的必备分析工具，是结合LBE实验数据的积累和对物理现象的理解而开发的。在这项研究中，开发了一个可用于 LBE 的子通道代码，并详细描述了典型子通道的相应几何表征方法，包括带有线间隔的燃料组件。对于这个子通道代码，考虑了通过间隙的横向热传导。此外，还对物理特性、传热模型、流阻模型和湍流混合模型进行了分析。最后，选择在THEADES（Thermal-hydraulics and Ads DESign）上进行的LBE热工水力实验作为该子通道码的评价数据，包括19根带网格间隔器和线间隔器的杆，计算结果良好与实验结果一致。