FIELD: processing and recycling wastes; nuclear physics.
SUBSTANCE: invention relates to the field of solid radioactive wastes treatment, in particular to the spent graphite (SG) at decommissioning of uranium-graphite reactors. Method of handling spent reactor graphite during decommissioning of uranium-graphite reactors involves preliminary temporary holding of graphite masonry, dismantling of masonry, packing of spent graphite into containers and burial in near-surface or deep burial place. Prior to dismantling of graphite masonry, water-based acrylic primer is impregnated with graphite blocks.
EFFECT: invention makes it possible to create additional protective safety barriers during dismantling of SG, transportation of graphite blocks and packing of SG into containers and to reduce collective radiation doses of personnel when handling SG during decommissioning of uranium-graphite reactors.
1 cl, 1 dwg, 1 tbl
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