Heat transfer to NaK flowing through unbaffled rod bundles

Verification and refinement of the one-dimensional analysis code for the integrated steam generators in an SFR

“…Kalish-Dwyer model [4] for the shell side and the Mori-Nakayama model [5] for the helical tube side of the DTBSG are used for the convection heat transfer analysis. Gunter-Shaw model [6] for the shell side and Mori-Nakayama model [4] for tube side are adopted for a calculation of the friction factor.…”

“…Gunter-Shaw model [6] for the shell side and Mori-Nakayama model [4] for tube side are adopted for a calculation of the friction factor. The fouling effect was ignored for a tube's inner wall.…”

The impact of tube bundle layout on the thermal and fluidic behaviour of liquid lead–bismuth eutectic in a helical-coiled once-through steam generator

“…The heat transfer characteristics of mercury over a staggered tube bank were investigated by Hoe et al [ 11 ] and they concluded that the local heat transfer coefficient varies over the tube area, and it is higher in the front stagnation point than that of the rear stagnation point of the tubes. Kalish et al [ 12 ] extensively studied the thermal behaviour of NaK in a 19-rod bundle structure, arranged in 90° crossflow and 45° oblique flows through the bundles. They found that the local heat transfer coefficient was lower for the 45° oblique layout, compared to the 90° arrangement.…”

Numerical Study of Liquid Metal Turbulent Heat Transfer in Cross-Flow Tube Banks

“…A 2D numerical model realized is used to recreate Abramov et al's results, and the study is then extended to triangular and rectangular tube bundles in a parameter range suitable to represent common values encountered for both fission and fusion applications, i.e., Pe = 7.670 × 10 2 -1.350 × 10 3 and S/D = 1.25-1.65 [5]. Throughout the paper, the lead-bismuth eutectic alloy (LBE), characterized by Pr = 2.21 × 10 −2 , is adopted as the modeling fluid.To assess the quality of the produced numerical results for this more general case, experimental and semi-analytical correlations for a turbulent cross-flow with Pr 1 fluid are used as a reference [15,16]. Both Steady-RANS (S-RANS, in which mean quantities are not allowed to evolve in time) and unsteady RANS (URANS) modeling approaches are tested for uniform and spatially varying Pr t models.…”