Conjugate heat transfer analysis of a heat generating vertical plate (Q860055)

In this paper it is developed the conjugate heat transfer analysis of a rectangular fuel element of a nuclear reactor dissipating fission heat into upward moving liquid sodium as coolant. There are considered both the two-dimensional heat conduction equation for the fuel element and the two-dimensional boundary layer equation for the coolant. Numerical results in the form of temperature temperature profiles, axial temperature profiles, and average Nusselt number are presented for a wide range of parameters such as aspect ratio, conduction-convection parameter, heat generation parameter, or the flow Reynolds number.