Critical Heat Flux in Convective Boiling in Nuclear Reactors.

Authors

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

Corresponding Author

Mahgoub, Mohamed

Subject Area

Mechanical Power Engineering

Article Type

Original Study

Abstract

To asses the safety margin of a light water reactor during the postulated loss of coolant accident (LOCA) it is important to predict the peak clad temperature. To perform such a task thermohydraulic codes to have been developed. Among the inputs to the computer codes, heat transfer equations which are used to determine the heat transfer coefficient in various heat transfer modes, Prediction of the critical heat flux (CHF) - as a limiting condition-is therefore of vital importance. The purpose of this paper is to recommend -based on the current state of knowledge - a set of correlationswhich are used to estimate the CHF in convective boiling. Also, for the present work a computer program is developed for the prediction of CHF.

Recommended Citation

Mahgoub, Mohamed (2021) "Critical Heat Flux in Convective Boiling in Nuclear Reactors.," Mansoura Engineering Journal: Vol. 7 : Iss. 2 , Article 8.
Available at: https://doi.org/10.21608/bfemu.1982.181599