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International Heat Transfer Conference 10

ISSN: 2377-424X (online)
ISSN: 2377-4371 (flashdrive)

EXPERIMENTAL AND NUMERICAL STUDIES ON HEAT TRANSFER AND FLOW CHARACTERISTICS OF A FUEL ROD WITH TRANSVERSE SQUARE RIBS

Kazuyuki Takase
Japan Atomic Energy Agency

R. Hino
Department of High Temperature Engineering Japan Atomic Energy Research Institute Tokai-mura, Ibaraki-ken, 319-11 JPN

Y. Miyamoto
Shibaura Institute of Technology, Japan

Norio Akino
Japan Atomic Research Institute, Ibaraki, Japan

DOI: 10.1615/IHTC10.2650
pages 245-250

Résumé

Experimental studies on heat transfer and flow characteristics of a fuel rod with transverse square ribs in gas-cooled nuclear reactors have been performed to investigate thermal-hydraulic performances of an augmented fuel rod under the same coolant conditions as the reactor operations. Three kinds of fuel rods were made for the experiments. Each rod has different ratio of pitch to rib height which is l0,20 and 40. Heat transfer coefficients and friction factors of the augmented fuel rod in the turbulent region were much higher than those of a concentric smooth annulus and a standard fuel rod without square ribs, and those empirical correlations were derived from the experimental data. Periodic fully developed turbulent flows with heat transfer from an inner wall in the two-dimensional roughened annuler channel were numerically calculated for one pitch length of the square rib using the k-ε turbulence model. The profiles of velocities, temperatures and local Nusselt numbers were predicted for each ratio of pitch to rib height. An overall Nusselt number estimated by the calculation was 14-25% higher than that of the experimental result for each ratio of pitch to rib height.

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