Abstract

A method of improving the computational reactor model in the IR program on the basis of the experimental data on the xenon power oscillations is presented. It is concluded on the basis of the deviation of the computed axial offset from experiment that the program requires adjustment. The program was modernized by replacing the dependence of the thermophysical parameters of the core on the specific rate of power release by solving the heat-conduction and heat-and-mass transfer equations. This is accomplished by means of the method and software used in the NOSTRA computer code, which were additionally improved by taking account of the influence of structural changes in the fuel on the thermal conductivity.

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