| 方形子通道内超临界流体流动传热CFD分析 |
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| 引用本文： | 顾汉洋,程旭,卢冬华.方形子通道内超临界流体流动传热CFD分析[J].核动力工程,2009,30(2). |
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| 作者姓名： | 顾汉洋 程旭 卢冬华 |
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| 作者单位： | 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 |
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| 基金项目： | 国家重点基础研究发展规划(973计划) |
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| 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.
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| 关 键 词： | 超临界水堆 计算流体力学 子通道 湍流交混 |
CFD Analysis of Thermal-Hydraulic Behavior of Supercritical Water in Square Sub-Channels |
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| GU Han-yang,CHENG Xu,LU Dong-hua.CFD Analysis of Thermal-Hydraulic Behavior of Supercritical Water in Square Sub-Channels[J].Nuclear Power Engineering,2009,30(2). |
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| Authors: | GU Han-yang CHENG Xu LU Dong-hua |
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| Affiliation: | 1.School of Nuclear science and Engineering;Shanghai Jiaotong University;Shanghai;200240;China;2.National Key Laboratory of Bubble Physics and Natural Circulation;Nuclear Power Institute of China;Chengdu;610041;China |
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| Abstract: | Investigations on the thermal-hydraulic behavior in the SCWR fuel assembly have obtained a significant attention in the international SCWR community.However,there is still a big deficiency in knowl-edge 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 co... |
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| Keywords: | Supercritical water-cooled reactor CFD Sub-channels Turbulent mixing |
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