[en] Reprocessing of spent nuclear fuel (SNF) formed at the nuclear power plant is the most promising procedure to decrease the volume of radioactive waste for long-term storage. ''The strategy and main lines of the development of the nuclear power industry in Russia in the XXI century'' envisages the development of power industry using thermal (TR) and fast (FR) reactors. It is obvious that the reprocessing of SNF from these reactors within a single plan will strongly decrease both capital and current investments owing to use of the uniform (common) infrastructure. At present only the hydrometallurgical procedures are developed for combined reprocessing of SNF TR and FR, which suggest utilization of the large volumes of aqueous solutions. The environmental safety of such radiochemical plants is provided by the procedures based on concentration of the aqueous solutions with subsequent preparation of solid forms of radioactive waste suitable for prolonged storage of disposal. At present, the economical effectiveness and environmental safety are the key requirements to radiochemical technologies. These requirements focus the attention on the non-aqueous procedures. In this paper we analyze the approach based on both non-aqueous and hydrometallurgical procedures for combined reprocessing of SNF TR and BR. The combination of the conversion of oxide SNF in nitrates in the nitrogen dioxide medium and extraction of the target component using tri-n-butyl phosphate (TBP) solutions in Freons is considered as a main procedure for SNF TR reprocessing. SNF TR is first fragmented and then voloxidized and converted in nitrates. Then, using solutions of dibutyl ether (DBE) in Freon HFC-134a nearly 90-95% of uranium can be recovered from the melt, which further treatment is not analyzed in this paper. As a result, the solid residue (∼10% to the initial SNF weight) is obtained, whose composition corresponds to SNF FR and, thus, can be reprocessed with it. SNF FR after fragmentation and voloxidation can be combined with the residue after SNF TR reprocessing mentioned above and then converted in nitrates. Uranium and plutonium from the resulting melt can be recovered with solutions of TBP in Freon HFC-134a and then used for preparing MOX fuel. The residue obtained can be either solidified as high- level waste (HLW) or it can be treated to remove light actinides (LA) for utilization in FR in the form of AMOX fuel. The cycle of our studies showed the possibility of combined reprocessing of SNF WWER and BN using low-temperature low-water procedures. This approach will allow to use the infrastructure of the full-scale radiochemical plant for SNF TR reprocessing for smaller scale reprocessing of SNF BR and also to attain the following advantages as compared to the common hydrometallurgical and well-known 'dry' procedures of SNF reprocessing: - sharp decrease in the volume of secondary radioactive waste; - absence of organic solvents; - rather low temperature (60-80 deg. C) of the process