Glass is a suitable matrix for rendering radioactive wastes harmless. Most components of the wastes are incorporated into the structure of the glass, and components which are incompatible with the glass can be incorporated into the glass matrix in the form of a dispersed phase [1]. The high chemical and mechanical stability of glass makes it possible to contain the radionuclides for a long period of time.Although it was suggested at first that glass be used to isolate high-level wastes, vitrification is now regarded as a promising and economically useful method for rendering harmless medium-level wastes as well [2]. The equipment for vitrifying in this case is not as complicated, and the requirements for the f'mal product are not so stringent. This is due to the relatively short storage time of the wastes 500-1000 years until safe levels of the content of radiotoxic components due to radioactive decay of 137,134Cs, 6~9~ are reached in the wastes. Furthermore, the high chemical stability of the glass greatly simplifies the requirements for the storage conditions of the wastes, and this makes it possible to use the most easily accessible method of disposal in surface burial sites.Laboratory tests are an integral part of the program of rendering wastes harmless, which is based on the concept of the construction of a multiharrier system for isolating the wastes. Such tests also make it possible to obtain prior to disposal dam On the stability of the matrices as one of tile main components of this system. A large amount of reliable d~m on the behavior of vitrified high-level wastes now exists (see, for example, [3, 4]). Most of these data explain the regularities in the behavior of vitrified medium-level wastes as well; this is confirmed by preliminary investigations of such wastes at the Moscow Purification Station under conditions of open disposal using the method of scanning electron microscopy [5, 6]. Nonetheless, differences in the composition, preparation technology, physical properties, and disposal conditions make it necessary to analyze carefully the behavior of materials in order to assess reliably their containment properties.Our objective in the present work is to analyze the changes in the structure of glass under conditions of open disposal according to the results of tests, performed over 7 or 8 years, on glass blocks with inclusions of medium level wastes from nuclear power plants.Glass-Aging Processes. Corrosion processes during long-time storage of glass are most completely systematized in [3, 4]. Seven basic stages of corrosion are distinguished [4].1. At the ion exchange/diffiasion stage water and (H +, H20, H3 O+) ions diffuse into the glass and are exchanged with alkali metal ions (Na +, Li+). This results in the formation of a layer depleted of alkali metals (reaction zone, gel layer). In some cases water can d~ into the glass without leaching or other structural rearrangements resulting in the formation of water inclusions, as happens, for example, in obsidians, which remain stable for thousand...