Schulenberg T,Starflinger J.Core design concepts for high performance light water reactors[J].Nuclear Engineering and Technology,2007,39(4):249-256.
[2]
姚朝晖,沈孟育,王学芳.压水堆堆内进口环腔及下腔室中冷却剂三维流动的数值模拟[J].核科学与工程,1996,16(3):229-234.Yao Zhaohui,Shen Mengyu,Wang Xuefang.Calculation simulation of 3-D coolant flow in the entrance annular and lower plenums at PWR[J].Chines Journal of Nuclear Science and Engineering,1996,16(3):229-234(in Chinese).
[3]
桂学文,蔡琦,邾明亮.双环路压水堆非对称入口条件下物理-热工特性研究[J].原子能科学技术,2010,44(增刊):216-221.Gui Xuewen,Cai Qi,Zhu Mingliang.Operation behaviors of pressure water reactor with double loops under asymmetrical inlet conditions [J].Atomic Energy Science and Technology,2010,44(Suppl.):216-221(in Chinese).
[4]
蔡宏,吴燕华,杨冬.低质量流速优化内螺纹管的传热特性试验研究[J].中国电机工程学报,2011,31(26):65-70.Cai Hong,Wu Yanhua,Yang Dong.Experimental investigation on heat transfer characteristics of low mass-flux optimized rifled tube[J].Proceedings of the CSEE,2011,31(26):65-70(in Chinese).
[5]
Sohankar A,Davidson L.Effect of inclined vortex generators on heat transfer enhancement in a three- dimensional channel[J].Numerical Heat Transfer,Part A:Applications,2001,39(5):433-448.
[6]
阎昌琪,孙中宁,孙立成.反应堆失水事故条件下热管段内的两相流逆向流动研究[J].核科学与工程,2001,21(3):223—227.Yan Changqi,Sun Zhongning,Sun Licheng.Research on two-phase countercurrent flow in reactor hot leg at the loss of coolant accident[J].Chinese Journal of Nuclear Science and Engineering,2001,21(3):223-227(in Chinese).
[7]
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):3356-3361.Wang Weishu,Lu Tong,Zhao Pengfei,et al.Experimental investigation on heat transfer of supercritical pressure water flowing in the sub-channel with square distribution in supercritical water cooled reactor [J].Proceedings of the CSEE,2014,34(20):3356-3361(in Chinese).
[8]
Islam M S,Hino R,Haga K,et al.Experimental study on heat transfer augmentation for high heat flux removal in rib-roughened narrow channels[J].Journal of Nuclear Science and Technology,1998,35(9):671-678.
[9]
Wang J H,Bo H L,Jiang S Y,et al.Numerical simulation on flow field of swimming pool reactor[J].Atomic Energy Science and Technology,2005,39(4):322-325.
[10]
Li Y,Zhou W X,Zhang J G,et al.Numerical simulation of three-dimensional flow through full passage and performance prediction of nuclear reactor coolant pump [J].Atomic Energy Science and Technology,2009,43(10):898-902.
[11]
Jeong H Y,Ha K S,Kwon Y M,et al.A dominant geometrical parameter affecting the turbulent mixing rate in rod bundles[J].International Journal of Heat and Mass Transfer,2007,50(5-6):908-918.
[12]
王福军.计算流体力学分析[M].北京:清华大学出版社,2004:24-158.Wang Fujun.Analysis of computational fluid dynamics- principle and application of CFD[M].Beijing:Tsinghua University Press,2004:24-158(in Chinese).
[13]
Lee K B,Jang H C.A numerical prediction on the turbulent flow in closely spaced bare rod arrays by a nonlinear k-ϵ model[J].Nuclear Engineering and Design,1997,172(3):351-357.
[14]
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.
[15]
Baglietto E,Ninokata H.A turbulence model study for simulating flow inside tight lattice rod bundles[J].Nuclear Engineering and Design,2005,235(7):773-784.
[16]
Heina J,Mantlik F.The structure of turbulent flow in finite rod bundles[C]//1st World Conf.Experimental Heat Transfer,Fluid Mechanics and Thermo dynamics.Amsterdam:Elsevier,1988:1712-1719.
[17]
Yakhot V,Orsazg S A,Thangam S,et al.Development of turbulence models for shear flows by a double expansion technique [J].Physics of Fluids(A),1992,4(7):1510-1520.
[18]
Krauss T,Meyer L.Experimental investigation of turbulent transport of momentum and energy in a heated rod bundle[J].Nuclear Engineering and Design,1998,180(3):185-206.
[19]
Manoranjan V S,Gomez M O.Alternating direction implicit method with exponential upwinding [J].Computers & Mathematics with Applications,1995,30(11):47-58 .
[20]
Lien F S,Leschziner M A.Assessment of turbulence- transport models including non-linear RNG eddy-viscosity formulation and second-moment closure for flow over a backward-facing step [J].Computers and Fluids,1994,23(8):983-1004.
[21]
Oldekop W,Berger H D,Zeggel W.General features of advanced pressurized water reactors with improved fuel utilization[J].Nuclear Technology,1982,59(2):212-227.