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This article is devoted to the development and study of new protective materials containing depleted uranium dioxide for increasing the capacity for γ-ray absorption. The materials were developed for use in multipurpose containers for spent nuclear fuel. The results of work on obtaining high-density concrete and cermet are presented. The recipe and technology for fabricating concrete (RZK-VNIINM) with density 6.5 g/cm 3 have been patented. A method of obtaining a high-density composition of corrosion-resistant steel and depleted uranium dioxide (cermet) with density 8.3 g/cm 3 has been developed.Maximum capacity for given mass and size characteristics is one of the main requirements of the construction of multipurpose universal containers for spent nuclear fuel. Essentially, this requirement means that this construction is economically efficient. At present, the operating characteristics of metal-concrete containers are the reference points for evaluating the specific cost of transporting and storing spent nuclear fuel. For this reason, in developing new materials for containers the specific cost of the material used for biological protection was comparable to that of the metal-concrete structures.

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