ИСТИНА

In the nuclear industry, the problem of radioactive waste disposal is not yet fully solved, in particular the safe handling of 99Tc, which is a long-lived radionuclide with low sorption activity of its pertechnetate ion in relation to many materials. To solve this problem, various matrices were proposed for its immobilization, however, it became evident during the course of investigations that they were insufficient because of the high leaching degree of the pertechnetate ion. To increase the safety of the storage facility, it is necessary to use new materials to ensure effective and longterm immobilization of technetium as part of mineral matrices and geochemical barriers in the storage area. Activated carbon of different nature was widely used for this purpose [1 - 3]. In the experiments, the sorption characteristics of such activated carbons as birch activated carbon (BAU), activated graphite (AG-3) and coconut activated carbon (KAU), possessing a developed specific surface with respect to potassium pertechnetate have been studied. It has been established that sorption equilibrium is reached in less than 24 hours. At the same time, these materials showed high degrees of sorption and coefficients of interphase distribution, which depend on the area of the specific surface of the images.