Abstract
During the refueling of PWR, the spent fuel assemblies are transferred from the reactor building to the fuel building through an underwater tube. The heat transfer characteristics of the spent fuel assembly in the top-corner area of the carrier with poor heat transfer conditions is important for the safety design. Experiments were carried out and single phase natural convection and pool boiling heat transfer coefficients of the three fuel rods in the top-corner area of the carrier under different heat flux was measured and obtained. The new correlations were presented. The results can provide a reference for evaluating the thermal safety state and the maximum surface temperature of the fuel assembly during the transportation process in future engineering applications.
Highlights
To avoid the overheating of the assembly, it is necessary to study the heat transfer of the fuel assembly in the transfer tube to find out that whether the decay heat of the fuel assembly can be removed only rely on natural convection cooling
This paper present an experiment to study the natural convection heat transfer on the cross-section which is affected by the carrier
Where htop is the boiling heat transfer coefficient of the top corner of the fuel elements with unit of W · m−2 · K−1; q is the heat flux of the heating rod surface with the unit of W · m−2; k is liquid heat transfer coefficient with the unit of W · m−1 · K−1; hfg is the latent heat of vaporization with the unit of J · kg−1;Pr is the Prandtl Number;l∗ is the characteristic length
Summary
It is important for the design of a fuel transfer device to consider the hypothetical accidents such as the mechanical failure and loss of power supply. In this situation, the spent fuel assembly may be trapped in the transfer tube. The water flows back to the pool through the upper part of the tube
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