Natural Convection Heat Transfer in the Horizontal Dry Storage System for the LWR Spent Fuel Assemblies.

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  • NISHIMURA Motohiko
    Nuclear Systems Division, Kawasaki Heavy Industries, Ltd. O-arai Engineering Center, Power Reactor and Nuclear Fuel Development Corp.
  • SHIBAZAKI Hiroaki
    Kanto Technical Institute, Kawasaki Heavy Industries, Ltd.
  • FUJII Sadao
    Kanto Technical Institute, Kawasaki Heavy Industries, Ltd.
  • MAEKAWA Isamu
    Nuclear Systems Division, Kawasaki Heavy Industries, Ltd.

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  • Natural Convection Heat Transfer in the

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Abstract

A heat transfer and flow visualization experiment was conducted with a one-fifth scale model simulatinga dry shielded canister (DSC) with 24 PWR spent fuel assemblies in order to elucidate the heat transfer characteristics and the velocity distribution for natural convection inside a DSC filled with air or water at atmospheric pressure. It was found that the average heat transfer coefficients were proportional to the onefourth power of the Rayleigh number despite the complicated geometry inside the DSC. Flow patterns inside the DSC were visualized clearly through a digital image processing system. The velocity distributions inside the DSC were obtained quantitatively from the Particle Tracking Velocimetry. In comparison with the results of a two-dimentional thermal hydraulic analysis, computed flow patterns were similar to the experimental results and the computational temperature distributions on the sleeve surfaces agreed well with the experiments within 8%, except at the top point of the center gap. It was also found that the difference in the heat transfer coefficient was within 25% for air as the working fluid, while a satisfactory agreement was not obtained when water was the working fluid.

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