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首先利用先进子通道分析程序(ATHAS)对超临界水冷堆(CGN-SCWR)的双排棒组件进行子通道分析,以考察燃料棒包壳温度等热工参数是否达到安全要求。根据分析结果结合子通道水力直径和冷却剂出口温度,选取一些典型子通道的热工参数结果做详细比对,了解组件中不同类型子通道内的热工参数变化对组件性能的影响。另外,对子通道计算采用的湍流交混系数、轴向摩擦系数和传热关系式进行敏感性分析,以了解经验关系式对计算结果的影响。结果显示:所有热工参数结果均达到设计要求,包壳最高温度为685.3℃,且不同传热关系式的选择对包壳温度的影响明显,最大温差达到了41.3℃。
First, sub-channel analysis was performed on the double row rod assembly of Supercritical Water Cooled Reactor (CGN-SCWR) by using the advanced subchannel analysis program (ATHAS) to investigate whether the thermal parameters such as the cladding temperature of the fuel rod meet the safety requirements. According to the results of the analysis and the sub-channel hydraulic diameter and coolant outlet temperature, the thermal parameters of some typical subchannels are selected and compared in detail to understand the influence of the variation of thermal parameters in different subchannels on the performance of the module. In addition, the sensitivity analysis of turbulence mixing coefficient, axial friction coefficient and heat transfer relationship used in subchannel calculation is carried out to understand the influence of empirical relationship on the calculation results. The results show that the results of all the thermal parameters meet the design requirements. The maximum temperature of the cladding is 685.3 ℃. The influence of different heat transfer relation on the cladding temperature is obvious, and the maximum temperature difference reaches 41.3 ℃.