| 摘要 |
FIELD: radiochemical industry; nuclear power engineering.SUBSTANCE: invention relates to and is aimed at obtaining a mixed dioxide (U,Pu)O, which can be used for production of mixed uranium-plutonium MOX fuel for VVER-1000 reactors and fast neutron reactors (BN-600, BN-800) at nuclear power stations. Method of producing solid plutonium dioxide solution in uranium dioxide matrix includes: reacting of nitrate complexes of uranium and plutonium having their relative content in the solution of 95-70 and 5-30 wt% correspondingly with hydrazine hydrate in the molar ratio of - hydrazine hydrate: uranium, plutonium - equal to 2 in order to produce a mixed amorphous compound of uranium and plutonium, maintenance of the mixed amorphous compound of uranium and plutonium in mother solution at the temperature of 80-90 °C during at least 3.5 hours to obtain a fine powder sediment of homogeneously mixed hydrated uranium and plutonium dioxides, separation of the sediment from mother solution and its heating to the temperature of 280-300 °C till obtaining the target product.EFFECT: invention provides cost-effective, simple and less energy consuming method of producing solid plutonium dioxide solution in a uranium dioxide matrix.1 cl, 6 dwg, 2 ex |
