不同搅混翼定位格架5×5棒束通道内流动与传热特性数值研究
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摘要
建立了一组不同搅混格架的5×5棒束通道数值计算模型,以压降值、轴向及周向Nu分布为参考,将数值计算结果与文献中实验结果进行了对比验证,均取得了良好的吻合度。对两种具有不同形状搅混翼的棒束通道进行了数值模拟,比较分析了其流动及传热特性;通过引入三个无量纲因子:涡流搅混因子、交叉流搅混因子以及湍流强度因子,对其搅混作用进行了进一步的评价和比较。
A set of CFD models were setup to simulate the characteristics of flow and heat transfer in 5×5rod bundles with different spacer grids.Using pressure drop,lateral and axial distributions for the Nusselt number as references,the numerical results were validated by corresponding experimental data in the literature,and the numerical results agree reasonably well with the experimental data.The rod bundles with two types of mixing vane were simulated.The performance of two vanes was evaluated by the comparison of the characteristics of flow and heat transfer.Three dimensionless factors including swirl factor,cross-flow factor and turbulence intensity factor are introduced for the further analysis of effect of vanes on flow mixing.
A set of CFD models were setup to simulate the characteristics of flow and heat transfer in 5×5rod bundles with different spacer grids.Using pressure drop,lateral and axial distributions for the Nusselt number as references,the numerical results were validated by corresponding experimental data in the literature,and the numerical results agree reasonably well with the experimental data.The rod bundles with two types of mixing vane were simulated.The performance of two vanes was evaluated by the comparison of the characteristics of flow and heat transfer.Three dimensionless factors including swirl factor,cross-flow factor and turbulence intensity factor are introduced for the further analysis of effect of vanes on flow mixing.
引文
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[7]朱晓静,刘六井,沈胜强.带有定位格架的超临界反应堆堆芯强制对流换热的数值模拟[J].核动力工程,2014,35(3):22-25.ZHU Xiao-jing,LIU Liu-jing,SHEN Sheng-qiang.Numerical study on forced convection in sub-channel with grid spacer in supercritical reactor core[J].Nuclear Power Engineering,2014,35(3):22-25.(in Chinese)
[8]HOLLOWAY M V,BEASLEY D E,CONNER M E.Single-phase convective heat transfer in rod bundles[J].Nuclear Engineering and Design,2008,238(4):848-858.
[9]HOLLOWAY M V,CONNER M E,CONOVER T A,et al.The effect of support grid design on azimuthal variation in heat transfer coefficient for rod bundles[J].Journal of Heat Transfer,2005,127(6):598-605.
[10]LIU C C,FERNG Y M.Numerically simulating the thermal—hydraulic characteristics within the fuel rod bundle using CFD methodology[J].Nuclear Engineering and Design,2010,240(10):3078-3086.
[11]CUI X Z,KIM K Y.Three-dimensional analysis of turbulent heat transfer and flow through mixing vane in a subchannel of nuclear reactor[J].Journal of Nuclear Science and Technology,2003,40(10):719-724.
[12]朱晓静,周盛,邱庆刚,等.标准型定位格架对超临界水在堆芯传热和流动影响的数值研究[J].热科学与技术,2016,15(1):7-12.ZHU Xiao-jing,ZHOU Sheng,QIU Qing-gang,et al.Numerical research on heat and mass transfer of supercritical water in reactor core with standard grids pacer[J].Journal of Theremal Science and Technology,2016,15(1):7-12.(in Chinese)
[13]邱庆刚,丁雅倩,朱晓静,等.定位格架对超临界水冷堆堆芯换热的影响[J].热科学与技术,2017,16(1):20-25.QIU Qing-gang,DING Ya-qian,ZHU Xiao-jing.Effect of grids pacer on heat transfer of supercritical water flows in reactor core[J].Journal of Thermal Science and Technology,2017,16(1):20-25.(in Chinese)
[2]LIU C C,FERNG Y M,SHIH C K.CFD evaluation of turbulence models for flow simulation of the fuel rod bundle with a spacer assembly[J].Applied Thermal Engineering,2012,40:389-396.
[3]熊万玉,陈炳德,肖泽军.棒束定位格架内单相流体三维流场研究[J].原子能科学技术,2005,39(4):326-329.XIONG Wan-yu,CHEN Bing-de,XIAO Ze-jun.3-D flow field of rod bundles with spacer grids[J].Atomic Energy Science and Technology,2005,39(4):326-329.(in Chinese)
[4]朱晓静,滕大伟,沈胜强.超临界反应堆堆芯中定位格架阻力特性影响数值研究[J].核动力工程,2014,35(4):39-42.ZHU Xiao-jing,TENG Da-wei,SHEN Shengqiang.Numerical analysis of effects of grid spacer on resistance characteristics within sub-channel of SCWR[J].Nuclear Power Engineering,2014,35(4):39-42.(in Chinese)
[6]NAVARRO M A,SANTOS A A C.Evaluation of a numeric procedure for flow simulation of a 5×5PWR rod bundle with a mixing vane spacer[J].Progress in Nuclear Energy,2011,53(8):1190-1196.
[7]朱晓静,刘六井,沈胜强.带有定位格架的超临界反应堆堆芯强制对流换热的数值模拟[J].核动力工程,2014,35(3):22-25.ZHU Xiao-jing,LIU Liu-jing,SHEN Sheng-qiang.Numerical study on forced convection in sub-channel with grid spacer in supercritical reactor core[J].Nuclear Power Engineering,2014,35(3):22-25.(in Chinese)
[8]HOLLOWAY M V,BEASLEY D E,CONNER M E.Single-phase convective heat transfer in rod bundles[J].Nuclear Engineering and Design,2008,238(4):848-858.
[9]HOLLOWAY M V,CONNER M E,CONOVER T A,et al.The effect of support grid design on azimuthal variation in heat transfer coefficient for rod bundles[J].Journal of Heat Transfer,2005,127(6):598-605.
[10]LIU C C,FERNG Y M.Numerically simulating the thermal—hydraulic characteristics within the fuel rod bundle using CFD methodology[J].Nuclear Engineering and Design,2010,240(10):3078-3086.
[11]CUI X Z,KIM K Y.Three-dimensional analysis of turbulent heat transfer and flow through mixing vane in a subchannel of nuclear reactor[J].Journal of Nuclear Science and Technology,2003,40(10):719-724.
[12]朱晓静,周盛,邱庆刚,等.标准型定位格架对超临界水在堆芯传热和流动影响的数值研究[J].热科学与技术,2016,15(1):7-12.ZHU Xiao-jing,ZHOU Sheng,QIU Qing-gang,et al.Numerical research on heat and mass transfer of supercritical water in reactor core with standard grids pacer[J].Journal of Theremal Science and Technology,2016,15(1):7-12.(in Chinese)
[13]邱庆刚,丁雅倩,朱晓静,等.定位格架对超临界水冷堆堆芯换热的影响[J].热科学与技术,2017,16(1):20-25.QIU Qing-gang,DING Ya-qian,ZHU Xiao-jing.Effect of grids pacer on heat transfer of supercritical water flows in reactor core[J].Journal of Thermal Science and Technology,2017,16(1):20-25.(in Chinese)