A SIMPLE COMPUTER PROGRAMME FOR THE CALCULATIONS OF REACTOR CHANNEL TEMPERATURE DISTRIBUTION

Abstract

This paper presents the results of THERMAL computer programme and checks its validity using KFKI reactor fuel channel as a sample problem of the implementation. The simple computer programme has been developed to perform the necessary calculation of axial temperature distribution along a multiregion channel, and other hydraulics parameters for any reactor coolant channel. The criteria of the temperature are such that the surface boiling should be avoided at any part of the cladding surface of the coolant channel. The results of the THERMAL compared with the results recorded in the reactor safety report are in good agreement. Finally, the results of this calculation at equilibrium and starting core with maximum and average core loading are given.