Аннотация:The article refl ects the problem of graphite-containing slurries accumulated, as deposit, in technological
systems during the operation of uranium-graphite reactors. Technical and methodological approaches to the
performance of work on the survey of containers are presented, which made it possible to remotely select highly
active samples of graphite-containing slurry from closed containers located in radiation-hazardous rooms, and to
estimate the volume, layer thickness, and surface profi le of deposits. Methods are described, including radiochemical
ones, used in the course of research to determine the radionuclide composition, activity levels, amounts of solid
and liquid phases, moisture content, and mass loss on ignition. To predict the behavior of radionuclides sorbed on
deposits, the selective desorption method was used to determine the water-soluble, ion-exchange, low-mobility,
strongly bound, and strongly fi xed forms of radionuclides in samples of graphite-containing slurry. The results
obtained were used to assess nuclear and radiation safety, as well as to develop technological methods for handling
graphite-containing slurries during the decommissioning of containers. Proven approaches to survey and laboratory
analysis of deposits can be used in the inspection of other similar containers containing high-level deposits.