METHOD OF PRODUCING SOLID PLUTONIUM DIOXIDE SOLUTION IN URANIUM DIOXIDE MATRIX

摘要

FIELD: chemistry.;SUBSTANCE: invention relates to the radiochemical industry and nuclear power engineering, is aimed at obtaining a mixed dioxide (U,Pu)O₂ and can be used to produce mixed uranium-plutonium MOX fuel for VVER-1000 reactors and fast neutron reactors (BN-600, BN-800) at nuclear power plants. The method of producing a solid plutonium dioxide solution in a uranium dioxide matrix includes reacting nitrate complexes of uranium and plutonium with relative content thereof in the solution of 95-70 wt % and 5-30 wt %, respectively, with hydrazine hydrate to obtain a mixed amorphous compound of uranium and plutonium, holding the mixed amorphous compound of uranium and plutonium in the mother solution at 80-90°C for not less than 3.5 hours to obtain a precipitate of a fine powder of homogeneously mixed hydrated plutonium and uranium dioxide, separating the precipitate from the mother solution and heating to 280-300°C to form the end product.;EFFECT: invention provides a cost-effective, simple and less energy consuming method of producing a solid plutonium dioxide solution in a uranium dioxide matrix.;2 cl, 6 dwg, 2 ex