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机构地区:[1]上海交通大学核能科学与工程学院,上海200240 [2]中国核动力设计研究院空泡物理和自然循环国家级重点实验室,成都610041
出 处:《核动力工程》2009年第2期1-5,共5页Nuclear Power Engineering
基 金:“973计划”项目(No.2007CB209804)资助
摘 要:国际上对超临界水冷堆进行了大量的研究,但对其堆芯内超临界流体流动传热特征的认识还十分欠缺。本研究采用CFX软件对典型超临界反应堆燃料组件子通道内的超临界热工水力特征进行了数值分析。研究了流动参数、边界条件和节径比(P/D)对子通道间交混现象和传热特性的影响。计算结果表明:燃料组件外围壁面子通道比内部子通道的湍流交混强烈;稠密栅格的湍流交混比宽栅格的湍流交混小。当P/D>1.2后,P/D比对湍流交混影响不再明显。研究还发现,在拟临界点附近区域,出现湍流交混系数的突变。Investigations on the thermal-hydraulic behavior in the SCWR fuel assembly have obtained a significant attention in the intemational SCWR community. However, there is still a big deficiency in knowledge and prediction of the heat transfer in supercritical fluids. In this paper, CFD analysis is carried out to study the thermal-hydraulic of supercritical water flows in sub-channels of a typical SCWR fuel assembly using commercial CFD code CFX 5.6. Effects of various parameters, such as flow parameters, boundary conditions and pitch-to-diameter ratios on the mixing phenomenon between sub-channels and heat transfer, are investigated. The mixing phenomenon due to cross flow between wall sub-channels is much stronger than that between regular sub-channels. The turbulent mixing in tight lattice (P/d=-1.1) is lower than that in wide lattice (P/d〉1.1), whereas, the effect of pitch-to-diameter ratio on the turbulent mixing is slight at P/d〉l.2. It also shows unusual behavior in the vicinity of the pseudo-critical point and further investigation is needed.
分 类 号:TK123[动力工程及工程热物理—工程热物理]
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