CFD investigation on thermal-hydraulic behaviors of a wire-wrapped fuel subassembly for sodium-cooled fast reactor

Hydrodynamic models and correlations for bare and wire-wrapped hexagonal rod bundles — Bundle friction factors, subchannel friction factors and mixing parameters

Shih-Kuei Cheng, N.E. Todreas · Nuclear Engineering and Design · 1986 · 421 citations

Engineering, Materials Engineering, Materials Science +10

A summary of sodium-cooled fast reactor development

Kazumi Aoto, Philippe Dufour, Hongyi Yang et al. · Progress in Nuclear Energy · 2014 · 230 citations

Engineering, Nuclear Engineering, Heat Transfer +11

CFD investigation of helical wire-wrapped 7-pin fuel bundle and the challenges in modeling full scale 217 pin bundle

R. Gajapathy, K. Velusamy, P. Selvaraj et al. · Nuclear Engineering and Design · 2007 · 79 citations

Engineering, Nuclear Engineering, Computational Fluid Dynamics +9

A comparative CFD investigation of helical wire-wrapped 7, 19 and 37 fuel pin bundles and its extendibility to 217 pin bundle

R. Gajapathy, K. Velusamy, P. Selvaraj et al. · Nuclear Engineering and Design · 2009 · 76 citations

Engineering, Materials Science, Nuclear Engineering +11

Turbulent flow simulation in a wire-wrap rod bundle of an LMFBR

K. Natesan, T. Sundararajan, Arunn Narasimhan et al. · Nuclear Engineering and Design · 2010 · 66 citations

Engineering, Civil Engineering, Mechanical Engineering +12