The objective of this paper is to investigate the transient thermal performance of a single cooling channel in a pressurized water reactor (PWR). A new developed two dimensional fuel rod code in which the radial and axial heat transfer are taken into consideration is used for calculation. This code is used to study the steady-state and transient temperature behaviour of nuclear fuel rods in light water reactors. In addition, the real thermodynamic conditions as the variation of the coolant heat transfer coefficient along the channel length and the gap thermal resistance- are taken into consideration. These real thermodynamic properties of the coolant are calculated using VDI correlations.
Ahmed Mahgoub, M. (2021). Transient Thermal Performance of a Single Cooling Channel in a PWR Reactor Core.. MEJ- Mansoura Engineering Journal, 15(2), 69-77. doi: 10.21608/bfemu.2021.171305
MLA
Mohamed Mahmoud Ahmed Mahgoub. "Transient Thermal Performance of a Single Cooling Channel in a PWR Reactor Core.". MEJ- Mansoura Engineering Journal, 15, 2, 2021, 69-77. doi: 10.21608/bfemu.2021.171305
HARVARD
Ahmed Mahgoub, M. (2021). 'Transient Thermal Performance of a Single Cooling Channel in a PWR Reactor Core.', MEJ- Mansoura Engineering Journal, 15(2), pp. 69-77. doi: 10.21608/bfemu.2021.171305
VANCOUVER
Ahmed Mahgoub, M. Transient Thermal Performance of a Single Cooling Channel in a PWR Reactor Core.. MEJ- Mansoura Engineering Journal, 2021; 15(2): 69-77. doi: 10.21608/bfemu.2021.171305
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