Patent Number: 040654001
Section: claims

1. A process for continuously solidifying high level radioactive waste resulting from reprocessing irradiated nuclear reactor fuels anc containing virtually all of the nonvolatile fission products, several tenths of one percent of the uranium and plutonium originally in the irradiated fuels, and other actinides formed by transmutation of the uranium and plutonium as normally produced in a nuclear reactor, by using a fluidized inert bed having a minimal fission product inventory comprising introducing an inert particulate material comprising silica particles having an average particle diameter of from about 0.20 to about 0.40 mm into a chamber; heating said material to from about 400.degree. to about 1300.degree. C; dispersing air as a fluidizing gas beneath said material to agitate same and form a fluidized bed; atomizing said radioactive liquid waste; introducing said atomized waste into an upper portion of said heated, fluidized bed to effect calcination of said waste and formation of a fluidized inert bed with said atomized waste comprising from about 10 to about 15 weight percent calcined radioactive waste and from about 90 to 85 weight percent silica particles, a first portion of said calcined waste being spray dried, a second portion of said calcined waste depositing and remaining on said particulate fluidized bed material, and a third portion of said calcined waste depositing on said bed material and attriting therefrom; removing solid calcine radioactive waste from said reactor chamber, said removing comprising elutriating said spray dried first portion, elutriating said attrited third portion, separating said elutriated solid calcine waste from said fluidizing gas, and overflowing said second portion from said fluidized bed at an about upper portion of said fluidized bed, said introducing of said atomized waste at an upper portion of said inert fluidized bed enhancing attrition and minimizing inert bed loss through overflow; introducing additional inert particulate material into said reaction chamber to maintain said inert fluidized bed; continuing said atomizing, calcining and removing of said solidified radioactive waste, and collecting said first, second and third portions removed from said fluidized inert bed as a readily vitrifiable product comprising about 90 weight percent calcined waste and about 10 weight percent silica, and having an average particle diameter of from about 0.1 mm to about 0.3 mm. 2. The process of claim 1 wherein said heating is at from about 400.degree. to about 800.degree. C. 3. The product formed by the process of claim 1. 4. The process of claim 1 wherein said high level radioactive liquid waste comprises from 320 to 575 liters of waste feed obtained from the processing of a metric ton of uranium, said feed materials yield from 80 to 210 grams of calcine per liter of liquid waste, and the concentration of sodium in said feed materials is from 0.01 molar to 1 molar said radioactive liquid waste is atomized at the rate of 20 to 40 liters per hour; and said heating is to a temperature of from about 500.degree. to about 800.degree. C.