目前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的认识还十分欠缺.本文采用CFX对超临界水冷堆典型子通道内的流动传热特征进行了CFD研究,对比分析了四边形和三角形布置的两类子通道流动传热特征.计算结果表明二阶SSG湍流模型能较好地模拟子通道内的超临界流体流动和传热特征.流动特征的分析表明四边形子通道内的二次流比三角形子通道内的复杂,强度也更大.两类子通道内的湍流脉动特征类似,当栅距较小时其间隙处的湍流交混系数都在0.02～0.025之间.四边形子通道的周向温度和换热不均匀性比三角形子通道的强烈.
参考文献
| [1] | Oka Y;Koshizuka S.Design Concept of Once-Through Cycle Supercritical Pressure Light Water Cooled Reactors[A].Tokyo,Japan,2000:1-22. |
| [2] | Yoo J;Shiwatari Y;Y Oka.Composite Core Design of High Power Density Supercritical Water Cooled Fast Reactor[A].Tsukuba,2006:246. |
| [3] | Kazuhiro KAMEI;Akifumi YAMAJI;Yuki ISHIWATARI;Yoshiaki OKA;Jie LIU .Fuel and Core Design of Super Light Water Reactor with Low Leakage Fuel Loading Pattern[J].Journal of Nuclear Science and Technology,2006(2):129-139. |
| [4] | Yamagata K;Nishikawa K;Hasegawa et al.Forced Convection Heat Transfer to Supercritical Water Flowing in Tubes[J].International Journal of Heat and Mass Transfer,1972,15(12):2575-2593. |
| [5] | Oka Y;Ishiwatari Y;Koshizuka S.Research and Development of Super LWR and Super Fast Reactor[A].上海,2006:9-18. |
| [6] | X. Cheng;B. Kuang;Y.H. Yang .Numerical analysis of heat transfer in supercritical water cooled flow channels[J].Nuclear engineering and design,2007(3):240-252. |
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