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- W2078315487 abstract "Temperature distribution within the rod bundle of a nuclear reactor is of major importance in nuclear fuel design. However, a knowledge of the hydrodynamic behaviour of the coolant is a prerequisite to the determination of the temperature distribution. It is believed that a knowledge of the hydrodynamic behaviour of the coolant is the most difficult part of the problem due to the complexity of the turbulent phenomena. In the present work, however, three-dimensional heat transfer calculations have been performed subject to an assumption of axial uniform flow along the square duct. An analytical solution for this simple mathematical model has been obtained and provides a basis for comparison with the finite element solution of the heat transfer equation. Computer results appear to agree with the true solution to within 1%." @default.
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- W2078315487 date "1982-12-01" @default.
- W2078315487 modified "2023-09-28" @default.
- W2078315487 title "Finite element analysis of axial flow with heat transfer in a square duct" @default.
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- W2078315487 doi "https://doi.org/10.1016/s0307-904x(82)80010-3" @default.
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