Effects of wire-spacer shape in LMR on thermal–hydraulic performance
暂无分享,去创建一个
[1] L. F. Parsly,et al. Temperature distribution in the duct wall and at the exit of a 19-rod simulated LMFBR fuel assembly (FFM bundle 2A) , 1974 .
[2] R. J. Cena,et al. COBRA-IV-I: an interim version of COBRA for thermal-hydraulic analysis of rod bundle nuclear fuel elements and cores , 1976 .
[3] R. A. Markley,et al. Experimental investigations of the hydraulic field in wire-wrapped LMFBR core assemblies , 1980 .
[4] J. N. Lillington,et al. The SABRE code for fuel rod cluster thermohydraulics , 1984 .
[5] F. Menter. Two-equation eddy-viscosity turbulence models for engineering applications , 1994 .
[6] T. Coakley,et al. TURBULENCE MODELING VALIDATION , 1997 .
[7] E. Fernandez,et al. Static pressure and wall shear stress distributions in air flow in a seven wire-wrapped rod bundle , 2000 .
[8] Kyong-Won Seo,et al. An experimental study and assessment of existing friction factor correlations for wire-wrapped fuel assemblies , 2001 .
[9] Won-Seok Kim,et al. A subchannel analysis code MATRA-LMR for wire wrapped LMR subassembly , 2002 .
[10] Il Kon Choi,et al. Measurement of Pressure Drop in a Full-Scale Fuel Assembly of a Liquid Metal Reactor , 2003 .
[11] Kwang-Yong Kim,et al. Flow and convective heat transfer analysis using RANS for a wire-wrapped fuel assembly , 2006 .
[12] Kwang-Yong Kim,et al. Shape optimization of wire-wrapped fuel assembly using Kriging metamodeling technique , 2008 .
[13] S. Patankar. Numerical Heat Transfer and Fluid Flow , 2018, Lecture Notes in Mechanical Engineering.