Investigating empirical correlation of critical heat flux

During the recent decades, a vast amount of research has been devoted to fully understand critical heat flux phenomena. In this connection, different empirical and semi-empirical correlations has been suggested and presented in the well-known papers. The aim is to review and develop the C HF correlation. Due to the vital importance of C HF, the first chapter is devoted to the effect of parameters such as coolant inlet temperature, mass flux, channel length and diameter, pressure and other related parameters, on the C HF. To fully understand the C HF necessitates the exploration of fundamental heat transfer in two phase flow. In the second chapter topics such as flow pattern in vertical as well as horizontal channels, fundamentals of subcooled and saturated flow boiling, void fraction, pressure drop and related matters will be investigated and discussed. In the third chapter, some of Kate's empirical and semi empirical correlations will be presented and investigated. The fourth chapter is devoted to investigation of research reactor thermal hydraulics core. A thermal hydraulic code has been provided with FORTRAN language which considered a hot channel when the coolant changes phase, the aim of the code is to verify the following parameters for pool type research reactor. To determine quality, pressure, pressure gradient, temperature and void fraction along the channel. To determine safety margin parameters. To determine all pressure drop components along the channel. To determine maximum channel temperature and its location along the channel