The article analyses how some adverse external environmental factors impact on the protective properties of
concrete containers for storage and disposal of long-lived radioactive waste (RAW). Some conceptual issues of
storing (placing) and location of RAW containers in storages, which can significantly affect on the containers
durability during their exploitation, are discussed as well. A mathematical formalization is proposed, which allows
to perform general analysis of the potential effects of climatic, hydro-geological and other environmental factors on
the main operational characteristics of the ―container + RAW‖ system.
 

Balance evaluation for processing spent nuclear fuel of different origin at the plant RT-1 "Mayak" is performed. It is shown that at formation of vitrified high level waste the aluminophosphate matrix comprises a mixture of fission and transuranic radionuclides, which is not genetically related to the burn-up of nuclear fuel during operation of VVER-440 Rivne NPP. 

Alumina and alkali binders for cementing liquid radioactive wastes, which include boric acid compound were compared. Given the need for long-term keeping of insulating properties of the matrix at waste disposal as a condition of providing environmentally sound localization of conditioned waste residue, more promising is the use of alkaline binders. Comparison was made of alumina and alkali binders for cementing of liquid radioactive wastes, which include boric acid compound. 

Alumina and alkali binders for cementing liquid radioactive wastes, which include boric acid compound were compared. Given the need for long-term keeping of insulating properties of the matrix at waste disposal as a condition of providing environmentally sound localization of conditioned waste residue, more promising is the use of alkaline binders. Comparison was made of alumina and alkali binders for cementing of liquid radioactive wastes, which include boric acid compound. Keywords: liquid radioactive waste, bottoms, nuclear power plant, cementing, binding materials. 

The possibility of immobilizing the salts of evaporation residues of NPP liquid waste in matrices based on natural minerals is studied. It is shown that at salt content in the residue of 10 mass.% the glass-ceramic samples composed of clinoptilolite—montmorillonite—glass powder have a high chemical resistance (leaching rate of Cs-137 and Sr-90 radionuclides does not exceed 1 10-6 g/(cm2 day)).

The rate of self-decontamination of water masses from radionuclides in the most contaminated water bodies in Ukraine is determined. It is shown that the content of 137Cs in the water masses of the exclusion zone water bodies is reduced with halftime of decontamination of 9,6 1,4 years. The mechanism of slowing the rate of decontamination of water masses from radionuclides is considered. It is shown that two years after the radionuclide ingress in the water body there is a significant slowdown in the rate of purification of water masses.

The paper contains a review of the main provisions of the updated Decommissioning Concept for the operating NPPs in Ukraine. The presented results of analysis are based on the consideration of six possible scenarios of the nuclear power complex development for the 15- and 20-year lifetime extension of the units, as well as the results of strategic planning and a long-term forecast of the operating NPPs decommissioning activity for two main decommissioning options, namely the deferred dismantling and immediate dismantling. Comparative cost estimations for the WWER-440 and WWER-1000 units decommissioning are given for the acting and the updated Concept.