Sayenko S. Glassceramic materials on the base of natural components for nuclear spent fuel isolation

Object of investigation – crystalline phases of feldspar Na(K,Ca)AlSi3O8, quarts SiО2, mullite 3Al2O32SiО2 and kaolin clay in the glass-phase matrix, aim of investigation – obtaining the protective glass-ceramic materials of alumino-silicate composition, determining the main characteristics before and after gamma-irradiation. Methods of investigation: sintering under pressure, optic and electron microscopy, Xray analysis, InfraRed-spectroscopy, atom-emission spectroscopy with induced-coupled plasma and nuclear-physics methods for composition analysis, tests of physico-mechanical properties. Theoretical and practical results, novelty: the functional dependence was obtained between physico-chemical and mechanical characteristics of glass-ceramic compositions and parameters of their manufacturing by sintering under pressure using the natural raw on the basis of granite and kaolin clay. On the base of results of corrosion and radiation tests, the ability of glass-ceramic materials to ensure chemical resistance in water as well as radiation durability is shown. To solve the problem of reliable isolation of nuclear spent fuel, the method of its encapsulating into the protective form made from corrosion- and radiation-resistant glass-ceramic materials is proposed. Degree of introduction: technological rule of sintering under pressure, which is used in pilot-scale production of the NSC KIPT. Field of application: materials-science of ceramics and glass, radiation materials-science, solid state physics.