The realization of the process of treatment of organic radioactive waste (RW) containing tributilphosphate (TBP) in hydrocarbon solvent under the laboratory conditions is considered in this work. The main parameters of the process have been investigated as well as the characteristics of the final process product — sodium-aluminiumphosphate glass matrix.

The structure of the glass obtained by incorporation of the residue from reprocessing of the spent extractant, tributyl phosphate, into sodium aluminophosphate glass and the structural state of uranium in this glass were studied by vibration (IR, Raman) and X-ray absorption (XAFS) spectroscopy. An IR and Raman spectroscopic study shows that the structural network of the glasses is formed by ortho-and pyrophosphate groups linked by tetrahedral AlO 4 units. As follows from the XAFS data, uranium is present in the glass in the form of uranyl ions and of separate UO 2+x particles. The glass has high hydrolytic durability: The uranium leach rate determined in accordance with GOST (State Standard) R 52 126-2003 is of the order of 10 -8 g cm -2 day -1 .

In this paper the method of activity measurement of spent radionuclide sources (SRS) based on Co-60 and Cs-137 placed in well-type storage facilities, in order to forecast the SRS activity which can be placed at this facility is described. The distribution of the absorbed dose through the absorption material is measured with the help of the described absorption spectrometer. This information allows determining the activity of individual radionuclides with the help of mathematical methods.

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