Abstract
Ultraphosphate glass is proposed for immobilization, taking account of the composition of the plutonium-containing wastes at the Mining-Chemical conglomerate. Some parameters of the process of immobilizing in ultraphosphate glass model wastes with plutonium content up to 150 mg/liter are investigated. A preliminary study is made of the degree of inclusion of plutonium dioxide, the chemical stability of the ultraphosphate glass obtained, and the distribution of plutonium in it. It is shown that almost 2 times more plutonium dioxide is included in ultraphosphate glass than in phosphate glass. With respect to the main physicochemical parameters, specifically, component leachability, ultraphosphate glass can be regarded as promising for immobilizing liquid plutonium-containing wastes.
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