Abstract
Laboratory investigations of the strength and chemical resistance of the final product of thermochemical reprocessing of reactor graphite wastes in the Al-TiO2-C system are presented. The 137Cs and 90Sr leaching rate, which is determined for samples synthesized from a charge with real irradiated graphite from an AM research reactor, does not exceed 10−6 g/(cm2·day) at the 28th day.
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