Vitrification of liquid radioactive wastes containing transplutonium elements and investigation of properties of solidified products

Description of the pilot installation for the vitrification of real high-level radiactive wastes (boiled down raffinate after extraction WWER fuel reprocessing) is presented and the order of its operation is considered. Investigation of physicochemical properties of vitrification productsphospate glasses - is conducted with the use of the methods of radiochemical, differential thermal, and X-ray phase analyses by the measuring of melt electric conductivity and determining glass hydrolytic stability. Practically full incluson of TPE to a glass matrix is noted. Specific alpha activity of the prapared glass blocks with 0.5 kg constitutes approximatelly 7.85x1012 Bk/kg. Rate of TPE istope leaching by water from vitrification products reaches 10-8 g/(cm2xday) in several weeks and stays practically constant during a year and a half