Transient Thermal Performance of a Single Cooling Channel in a PWR Reactor Core.

Authors

Mohamed Ahmed Mahgoub, Associate Professor., Mechanical Power Engineering Department., Faculty of Engineering., El-Mansoura University., Mansoura., Egypt.

Corresponding Author

Ahmed Mahgoub, Mohamed

Subject Area

Mechanical Power Engineering

Article Type

Original Study

Abstract

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.

Recommended Citation

Ahmed Mahgoub, Mohamed (2021) "Transient Thermal Performance of a Single Cooling Channel in a PWR Reactor Core.," Mansoura Engineering Journal: Vol. 15 : Iss. 2 , Article 19.
Available at: https://doi.org/10.21608/bfemu.2021.171305