No abstract available

[en] Hydrolysis of U⁶ in the solutions is investigated using the methods of ion exchange and spectrophotometry using an ability of uranium ions to give coloured complexes with organic reagents (arsenazo-1 and arsenazo-3). It is shown that at uranium (6) concentration < 10^-5 mol/l in the 2.0-5.0 pH range only mononuclear U⁶ hydroxocomplexes are formed in the solution. The first constant of uranyl-ion hydrolysis is determined (K₁=3.7H10^-4 at μ=0.5(HNO₃+NaNO₃) and temperature +20 deg C)

[en] Using the methods of ultrafiltration, dialysis, centrifugation, migration in the electric field and adsorption on glass the state of microamounts (10^-7 mol/l) Fesup((3)) (Fe) in solutions and in the presence of trilone B in pH range 1.0-12.0 has been studied. The region of ion and pseudocolloid state of Fesup((3)) at different concentrations of trilone B in solutions is established. Possible mechanism of trilone B effect on the state Fesup((3)) microamounts in solutions is discussed

[en] The IAEA activity in the area of radioactive waste management mainly concentrates on three areas, namely: (i) the establishing of international principles and standards for the safe management of radioactive waste; (ii) to promote the development and improvements of waste processing technologies, including handling, treatment, conditioning, packaging, storage and disposal of waste; and (iii) assisting developing Member States in establishing good waste management practice through dissemination of technical information, providing technical support and training. These activities are carried out by the Waste Technology Section, Department of Nuclear Energy, and the Waste Safety Section, Department of Nuclear Safety. The Waste Technology Section's activities are organized into four subprogrammes covering: the handling, processing and storage of radioactive waste; radioactive waste disposal; technology and management aspects of decontamination, decommissioning and environmental restoration; and waste management information and support services

[en] The present IAEA activities in radioactive waste management, components of the program and particular projects, the existing mechanism for information collection, analysis and distribution are outlined. The role of the IAEA as a forum for information exchange, for coordinating common efforts in waste technology development and as an international body for direct assistance of Member States is discussed. Current IAEA projects and recent achievements in related waste management areas are summarized and highlighted

No abstract available

[en] The sorption ability of a number of hydrolizing elements relativel to KU-2x8 cationite is investigated. It is shown that mononuclear UOsub(2)(OH)sub(n)sup(2-n) and Sc(OH)sub(n)sup(3-n) hydrocomplexes reveal increased sorption ability as compared with UO₂²⁺- and Sc³⁺-ions. At the same time Pu(OH)sub(n)sup(4-n), Fe(OH)sub(n)sup(3-n), Cr(OH)sub(n)sup(3-n) possess a lower sorption ability than the sorption ability of Pu⁴⁺-, Fe³⁺-, Cr³⁺-ions. It is shown that with the formation of polynuclear Pusup((4)) and Usup((4)) hydrocomplexes in the solution, the sorption ability of these radioelements decreases relatively to KU-2x8 cationite

[en] The main part of the European territory of the former USSR contaminated after the Chernobyl accident belongs to Byelorussia. Twenty-three percent of its territory has been contaminated above 87.0 kBq/sq.m. Measurements undertaken have shown that the density of radioactive contamination is very different, the compositions of radionuclides and isotopes also differ in various contaminated regions. The protective measures taken in the republic were not sufficient, adequate and done in time due to several reasons. The paper describes some effects of the Chernobyl accident on economic, health and social situation in the republic. The experience in protective actions got in the five years after the accident in agricultural, industrial and social activities allow to formulate some results and conclusions on the post-accident situation in the republic. (author)

[en] The accident at Chernobyl NPP has led to the release of radioactive materials and the contamination of huge territories, where hundreds of thousands inhabitants are living. The liquidation of the accidents results includes enormous volume of decontamination work done and still being done at the NPP site, in the evacuation zone and in the contaminated regions from which the population was not relocated. In the last case decontamination is one of the protective measures activities undertaken to ensure safety of the population. The complex of decontamination work and associated with it radioactive waste treatment arid waste disposal claims for solving a number of technical and managerial problems, part of which should still be worked out. (author)

[en] In this work information is presented on the installation which is being developed for treatment of liquid radioactive waste. The characteristics of liquid waste generated during decontamination of industrial facilities in Republic of Belarus are also presented. The results of treatment of simulated liquid waste for ¹³⁷Cs removal using the method of chemical coprecipitation at different ratios of sedimenting reagents are described. The received data are juxtaposed with the results of sedimentation kinetics of nickel ferrocyanide at the same conditions. The last-named data were obtained by the methods of optical spectrophotometry and radioactive tracers. Methodology of synthesis and properties of cation-exchange fiber FIBAN K-1 modified by cobalt ferrocyanide is described. This sorbent has high sorption ability towards ¹³⁷Cs and may be used at the liquid waste treatment facility