Apparatus for recovering nuclear fuel from scrap material

Chemical apparatus and process disinfecting – deodorizing – preser – Chemical reactor – For radioactive reactant or product

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2523011W, 423 4, 423 20, 422189, B01J 100, G21F 930

Patent

active

042306728

ABSTRACT:
Process for recovering compounds of enriched nuclear fuel from scrap materials is disclosed. The process yields an acid solution with the nuclear fuel dissolved therein. Except for spent filter media, the scrap materials are calcined to produce an oxidized material, which is reduced to a particulate material and leached in an acid bath that contains some recycled acid to yield an acid solution of the nuclear fuel material. The scrap materials comprised of spent filter media are mulched and contacted with the acid solution. The insoluble materials are separated from the acid solution, and at least a portion of the acid solution is recycled to the leaching step, while the remainder of the acid solution is collected for subsequent treatment to recover the dissolved nuclear fuel material. Apparatus for performing the foregoing process is also disclosed.

REFERENCES:
patent: 3488162 (1970-01-01), Towski
patent: 3578419 (1971-05-01), Welty
patent: 3776856 (1973-12-01), Scheffler et al.
Thompson et al., "Fluidized Bed Calcination of Radioactive Wastes using In-Bed Combustion Heating", Nuclear Technology, vol. 16, Nov. 1972, pp. 396-405.

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