超临界水冷堆类三角形子通道流动传热特性研究
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摘要
基于类三角形子通道超临界水的传热试验,建立了超临界水冷堆三角形子通道物理模型。采用雷诺应力湍流模型SSG,在压力为23~28 MPa、质量流速为700~1 300kg/(m~2·s)、热流密度为200~1 000kW/m~2参数范围内,对棒径8mm、栅距比为1.4的子通道内超临界水流动与传热特性进行了数值研究。分析了系统参数对流动和传热特性的影响,对比了不同焓区的二次流特性。结果表明:采用SSG模型对超临界水冷堆三角形子通道内流动传热的CFD模拟结果与试验数据较吻合。质量流速越高,传热能力越强;子通道换热系数峰值随压力的提高而减小;热负荷越高,内壁温度越高;在大比热容区换热系数峰值随热流密度的增大而明显减小,传热存在恶化趋势。超临界区子通道内在与主流垂直方向形成了明显的二次流,存在6个对称的漩涡,二次流速最大值出现在子通道窄缝区间隙。通道内不同焓区二次流结构相似,但二次流强度随焓的提高而增大。
The physical model of the sub-channel within a triangular rod bundle,of which the rod diameter is 8 mm and the pitch-to-diameter ratio is 1.4,was built to numerically investigate the flow and heat transfer characteristics of supercritical water in the sub-channels of supercritical water-cooled reactor.The numerical investigation was performed within the range of pressure from 23 to 28 MPa,mass fluxes from 700to1 300kg/(m~2·s),and heat fluxes from 200 to 1 000kW/m~2.By using the Reynolds stress turbulence model SSG,the effects of mass flux,pressure and heat flux on the flow and heat transfer characteristics were analyzed in detail,as well as the secondaryflow characteristics in different enthalpy regions.The results show that the numerical results agree well with experimental results.The higher the mass flux is,the better the heat transfer performs.In the pseudo-critical enthalpy region,the peak of heat transfer coefficient decreases greatly with the increase of pressure and heat flux.The high heat flux induces high inner wall temperature and might cause the heat transfer deterioration.The obvious secondary flow is found in the direction perpendicular to the main flow,and six symmetrical vortices are formed in the cross section of sub-channel.The velocity of the secondary flow reaches a peak near the narrow gap.Although the structures of the secondary flow are similar in different enthalpy regions,the secondary flow velocity increases with bulk enthalpy.
The physical model of the sub-channel within a triangular rod bundle,of which the rod diameter is 8 mm and the pitch-to-diameter ratio is 1.4,was built to numerically investigate the flow and heat transfer characteristics of supercritical water in the sub-channels of supercritical water-cooled reactor.The numerical investigation was performed within the range of pressure from 23 to 28 MPa,mass fluxes from 700to1 300kg/(m~2·s),and heat fluxes from 200 to 1 000kW/m~2.By using the Reynolds stress turbulence model SSG,the effects of mass flux,pressure and heat flux on the flow and heat transfer characteristics were analyzed in detail,as well as the secondaryflow characteristics in different enthalpy regions.The results show that the numerical results agree well with experimental results.The higher the mass flux is,the better the heat transfer performs.In the pseudo-critical enthalpy region,the peak of heat transfer coefficient decreases greatly with the increase of pressure and heat flux.The high heat flux induces high inner wall temperature and might cause the heat transfer deterioration.The obvious secondary flow is found in the direction perpendicular to the main flow,and six symmetrical vortices are formed in the cross section of sub-channel.The velocity of the secondary flow reaches a peak near the narrow gap.Although the structures of the secondary flow are similar in different enthalpy regions,the secondary flow velocity increases with bulk enthalpy.
引文
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[18]WANG H,BI Q C,YANG Z D,et al.Experimental and numerical study on the enhanced effect of spiral spacer to heat transfer of supercritical pressure water in vertical annular channels[J].Applied Thermal Engineering,2012,48(15):436-445.
[19]于意奇,顾汉洋,程旭,等.不同棒束结构稠密栅元通道内的湍流CFD研究[J].原子能科学技术,2012,46(4):396-403.YU Yiqi,GU Hanyang,CHENG Xu,et al,CFD simulation on turbulent flow in lattice fuel assemblies[J].Atomic Energy Science and Technology,2012,46(4):396-403(in Chinese).
[20]路统.超临界水冷堆类三角形子通道内超临界水传热的试验研究[D].郑州:华北水利水电大学,2015.
[2]SHITSMAN M E.Impairment of the heat transmission at supercritical pressures[J].High Temperature,1963,1:237-244.
[3]ACKERMAN J W.Pseudoboiling heat transfer to supercritical pressure water in smooth and ribbed tubes[J].Journal of Heat Transfer,1970,92(3):490-498.
[4]GRIEM H.A new procedure for the prediction of forced convection heat transfer at near-and supercritical pressure[J].Heat and Mass Transfer,1996,31(5):301-305.
[5]陈听宽,罗毓珊,胡志宏,等.超临界锅炉螺旋管圈水冷壁传热特性的研究[J].工程热物理学报,2004,25(2):247-250.CHEN Tingkuan,LUO Yushan,HU Zhihong,et al.Investigation on the heat transfer characteristics of supercritical pressure boiler spirally water wall tube[J].Journal of Engineering Thermophysics,2004,25(2):247-250(in Chinese).
[6]吴刚,毕勤成,王汉,等.超临界压力水在倾斜上升管内传热的试验研究[J].西安交通大学学报,2011,45(5):6-11.WU Gang,BI Qincheng,WANG Han,et al.Heat transfer characteristics of supercritical water in inclined upward tube[J].Journal of Xi’an Jiaotong University,2011,45(5):6-11(in Chinese).
[7]ZHU X J,BI Q C,YANG D,et al.An investigation on heat transfer characteristics of different pressure steam-water in vertical upward tube[J].Nuclear Engineering and Design,2009,239(2):381-388.
[8]WANG W S,BI Q C,GU H F,et al.An investigation on heat transfer to water flowing in vertical upward internally ribbed enhancement tube at supercritical pressure[J].Advanced Science Letters,2011,4(6-7):2 281-2 288.
[9]LI H Z,WANG H J,LUO Y S,et al.Experimental investigation on heat transfer from a heated rod with a helically wrapped wire inside a square vertical channel to water at supercritical pressures[J].Nuclear Engineering and Design,2009,239(10):2 004-2 012.
[10]WU G,BI Q C,YANG Z D,et al.Experimental investigation of heat transfer for supercritical pressure water flowing in vertical annular channels[J].Nuclear Engineering and Design,2011,241(9):4 045-4 054.
[11]WANG H,WANG W S,BI Q C,et al.Experimental study of heat transfer and flow resistance of supercritical pressure water in a SCWR subchannel[J].The Journal of Supercritical Fluids,2015,100:15-25.
[12]王为术,路统,赵鹏飞,等.超临界水冷堆类四边形子通道内超临界水的传热试验研究[J].中国电机工程学报,2014,34(20):3 356-3 361.WANG Weishu,LU Tong,ZHAO Pengfei,et al.Experimental investigation on heat transfer of supercritical pressure water flowing in the subchannel with square distribution in supercritical water cooled reactor[J].Proceedings of the CSEE,2014,34(20):3 356-3 361(in Chinese).
[13]YANG J,OKA Y,ISHIWATARI Y,et al.Numerical investigation of heat transfer in upward flows of supercritical water in circular tubes and tight fuel rod bundles[J].Nuclear Engineering and Design,2007,237(4):420-430.
[14]CHENG X,KUAN B,YANG Y H.Numerical analysis of heat transfer in supercritical watercooled flow channels[J].Nuclear Engineering and Design,2007,237(3):240-252.
[15]GU H Y,YU Y Q,CHENG X,et al.Numerical analysis of thermal-hydraulic behavior of supercritical water in vertical upward/downward flow channels[J].Nuclear Science and Techniques,2008,19(3):178-186.
[16]ZHU X J,MOROOKA S,OKA Y.Numercial investigation of grid spacer effect on heat transfer of supercritical water flows in a tight rod bundle[J].International Journal of Thermal Sciences,2014,76(2):245-257.
[17]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研究[J].核动力工程,2014,35(3):22-25.ZHU Xiaojing,LIU Liujing,SHEN Shengqiang.Numerical study on forced convection in subchannel with grid spacer in supercritical reactor core[J].Nuclear Power Engineering,2014,35(3):22-25(in Chinese).
[18]WANG H,BI Q C,YANG Z D,et al.Experimental and numerical study on the enhanced effect of spiral spacer to heat transfer of supercritical pressure water in vertical annular channels[J].Applied Thermal Engineering,2012,48(15):436-445.
[19]于意奇,顾汉洋,程旭,等.不同棒束结构稠密栅元通道内的湍流CFD研究[J].原子能科学技术,2012,46(4):396-403.YU Yiqi,GU Hanyang,CHENG Xu,et al,CFD simulation on turbulent flow in lattice fuel assemblies[J].Atomic Energy Science and Technology,2012,46(4):396-403(in Chinese).
[20]路统.超临界水冷堆类三角形子通道内超临界水传热的试验研究[D].郑州:华北水利水电大学,2015.