Mohammed G. A. Fawaz Author

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Numerical Heat Transfer Analysis in Vertical Rectangular Channels in the Core of a Typical Nuclear Research Reactor

Author(s): Said M. A. Ibrahim, Hesham F. Elbakhshawangy, Mohammed G. A. Fawaz

Numerical Heat Transfer Analysis in Vertical Rectangular Channels in the Core of a Typical Nuclear Research Reactor

The heat transfer characteristics for the case of turbulent forced and mixed convection flow of water through narrow vertical rectangular heated channel simulating a cooling channel of a typical material testing reactor (MTR) have been analysed and numerically investigated. Numerical solutions are performed on demineralized water as coolant passing under atmospheric pressure through narrow rectangular channel of 80 cm length, 7 cm width, and 2.7 mm gap thickness under different heat fluxes that covers almost all possible heat fluxes in the single-phase liquid... view more»

DOI: 10.4172/2325-9809.1000127

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