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带交混翼矩形流道内超临界流动传热CFD研究 被引量：2

CFD Study on Supercritical Water Flow and Heat Transfer in Rectangular Channel With Mixing Vane
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摘要 针对超临界水堆使用的棒束,取1根加热棒为中心的矩形区域作为研究对象,采用CFD中CFX10作为数值计算方法,研究了25 MPa超临界压力下,有无交混翼时流体的流动和传热特点。计算结果表明:交混翼可增加流道内温度分布的均匀性,同时具有强化传热作用。 In order to investigate the mixing vane effect on the characteristic of flow and heat transfer under 25 MPa pressure, numerical study was performed with CFX10 in a rectangular channel with a heating rod in center of it, which was modeled from fuel bundles of supercritical water reactor. The results indicate that mixing vane has the distribution of temperature in cross section of channel more uniformly than that without it, and heat transfer is enhanced by the mixing vane.
作者 卢冬华 顾汉洋 李永亮 闫晓
机构地区 中国核动力研究设计院空泡物理和自然循环国家重点实验室 上海交通大学核科学与工程学院
出处 《原子能科学技术》 EI CAS CSCD 北大核心 2009年第6期514-517,共4页 Atomic Energy Science and Technology
基金 国家重点基础研究发展计划资助项目(2007CB209803)
关键词 超临界反应堆 棒束 交混 数值流体力学方法 supercritical water reactor fuel bundles mixing CFD method
分类号 TL364.4 [核科学技术—核技术及应用]
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参考文献4

  • 1PHILIP M, JACOPO B, JAMES W S, et al. Feasibility study of supercritical light water cooled reactors for electric power production, INEEL/EXT-04-02530[R]. Pittsburgh, USA: Westinghouse Electric Co. , 2007.
  • 2KISS A, LAURIEN E, ASZODI A. Numerical simulation of an HPLWR fuel assembly flow with wrapped wire spacers[C]//International Students Workshop on High Performance Light Water Reactors. Karlsruhe, Germany: Karlsruhe Institute of Technology, 2007: 56-63.
  • 3KIRILLOV P L, OPANASENKO A N, POMETKO R S, et al. Experimental study of heat transfer on rod bundle at supercritical parameters of freon-12 [C]. Obninsk, Russian:Federal Agency for Atomic Energy State Scientific Center of RF-Institute for Physics and Power Engineering Named After A. I. Leypunsky, 2006: 131-136.
  • 4STEFFEN H, CLASS A G, LAURIEN E, et al. CFD analysis of subchannel flow in an HPLWR assembly with wire wraps[C]//International Students Workshop on High Performance Light Water Reactors. Karlsruhe, Germany: Karlsruhe Institute of Technology, 2008: 1-4.

同被引文献13

  • 1Oka Y,Koshizuka S.Design concept of once-through cycle supercritical pressure light water cooled reactors[C]//Proc of SCR-2000,Tokyo,Japan,2000:1-22.
  • 2Yoo J,Ishiwatari Y,Oka Y,et al.Composite core design of high power density supercritical water cooled fast reactor[C]//Proc of Global 2005,Tsukuba,Japan,2005:246-251.
  • 3Cheng X,Kuang B,Yang Y H.Nuclear analysis of heat transfer in supercritical water-cooled flow channels[J].Nuclear Engineering and Design,2007,237(3):240-252.
  • 4STEFFEN H,CLASS A G,LAURIEN,et al.CFD analysis of sub-channel flow in a HPLWR assembly with wire wraps[C]//International Students Workshop on High Performance Light Water Reactors.Karlsruhe,Germany:Ksrlstruhe Institute of Technology,2008:1-4.
  • 5Wagner W,Kruse A.The industrial standard IAPWS-IF97 for the thermodynamic properties and supplementary equations for other Propertics[C]//Properties of Water and Steam.Springer,Heidelber,1997:55-68.
  • 6Oka Y,Koshizuka S.Design concept of once-through cycle super critical pressure light water cooled reators[C] //Proc of SCR-2000,Tokyo,Japan,2000:1-22.
  • 7Yoo J,Ishiwatari Y,Oka Y,et al.Composite core design of high power density supercritical and design[J].Nuclear Engineering and Design,2007,237(3):240-252.
  • 8Cheng X,Kuang B,Yang Y H.Nuclear analysis of heat transfer in supercritical water-cooled flow channels[C] //Nuclear Engineerinical Water Cooled Fast Reactor.Proc of Global 2005,Tsukuba,Japan,2006:246.
  • 9Steffen H,Class A G,Laurien E,et al.CFD analysis of subchannel flow in an HPLWR assembly with wire wraps[C] // International Students Workshop on High Performance Light Water Reactors.Karlsruhe,Germany:Ksrlstruhe Institute of Technology,2008:1-4.
  • 10Wagner W,Kruse A.The industrial standard IAPW-S-IF 97 for the thermodynamic properties of Water and Steam[M].Springer-Verlag,Herelber-gx,1998.

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原子能科学技术
2009年 第6期

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