During operation of uranium-graphite reactors, waste graphite, containing fragments of nuclear fuel and fission products, as well as radioactive zirconium alloy components from fuel assemblies are produced. A large number of experiments should be carried out for the synthesis of appropriate matrix materials for radioactive nuclides that occur in these wastes. For the choice of processing technologies, an approach was used based on the thermodynamic simulation and application of self-sustaining reactions. A preliminary batch compaction and a hot pressing of the end product were not carried out. The end composite matrix product provides strong retention of the carbon-14 and other radionuclides. The processing technologies proposed are rather simple in implementation, can be realized without complex production equipment and energy supply.

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