ISSN (0970-2083)

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Research Article Open Access

Features of Fuel Burnup Calculations for Irt-T Reactor Using Mcu-Ptr Code


The article considers computation methods of the kinetics of changes of fuel nuclide composition vs. fuel burnup. Calculations were carried out at different intervals of operating time at a constant level of power of the IRT-T research reactor for different types of fuel assemblies. The analysis of the reaction rate of absorption for the isotopes included in the fuel composition is given. It is shown that the use of piecewise linear interpolation is the most preferred in order to calculate the long fuel campaigns as there is a high convergence of calculation data.

A. Naymushin *, M. Anikin, I. Lebedev, A. Busygin, S. Dmitriev And D. Zolotykh

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