The functional interpolation method for reactor core physics calculations

A novel methodology, the Functional Interpolation Method (FIM), has been developed. The FIM allows the calculation of control rod worth values and power distribution by means of a variational technique which utilizes a special set of trial functions.

This new methodology has been developed for a general multirodded region reactor using the one-group neutron diffusion model.

The FIM algorithm was validated by comparing its predictions to exact analytical solutions of a one-dimensional model of the Fast Flux Test Facility (FFTF) reactor. The outcome of this validation procedure was that given two exact reactor neutronics solutions at two specified reactor core configurations, the FIM methodology provides practically exact results for any intermediate reactor configuration.

Hence, the technique developed in this thesis allows the calculation of control rod worths and power distribution along a reactor fuel cycle, given the eigenvalues and flux profiles for two arbitrary picked points in the cycle.

In view of the algebraic simplicity of the algorithm, the FIM is ideally suitable for on-line computer calculations and hence for the development of reactivity and power distribution monitor systems.