Abstract
The present work is aimed to verification of the methodology designed to determine the energy release (heat release) in fuel detectors irradiated in tests at IGR and IVG.1M reactors. The paper presents the results of physical studies, when carrying out studies of thick uranium samples and fine powders from uranium dioxide where the energy release and the specific number of fissions were calculated. In the same way, the mass absorption coefficients of gamma quanta with energies of 756 and 1596 keV in uranium dioxide were determined. As a result, a comparative analysis of the correction factors for self-absorption and geometry for fuel pellets and powder preparations was made on the basis of which the correctness of the choice of this methodology for calculating the energy release.