US 4,230,672 AGranted

Apparatus for recovering nuclear fuel from scrap material

AssigneeGeneral Electric Company

InventorsLarry A. Divins, Larry E. Short

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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.

Claims3

Dependent claims

An apparatus for recovering nuclear fuel in solution form from scrap materials, including spent filter media, comprising in combination:

(a) calcining means for calcining the scrap materials other than the spent filter media to form an oxidized material that is fed to
(b) comminuting means for crushing the oxidized material into a particulate material of desired particle size for feeding to
(c) a slab-shaped leaching means for contacting the particulate material with an acid solution at a rate enabling substantially complete dissolution of the nuclear fuel portion of the particulate material with the aid of mechanical agitation means to yield an acid solution,
(d) mulching means for mulching the spent filter media to yield a mulched filter media in particulate form,
(e) filter leach and repulping means for receiving the mulched filter media containing nuclear fuel material and for receiving the acid solution from the leaching means in a manner that the mulched filter media is contacted with the acid solution and the nuclear fuel material held by the mulched filter media is substantially dissolved in the acid solution,
(f) separator means for receiving the acid solution with undissolved solids from means (e) and removing the nonsuspended undissolved solids from the acid solution, said separator means feeding the acid solution to
(g) leachate surge and reagent heat tank means for providing a constant output of the acid solution to
(h) clarification means that removes suspended solids from the acid solution,
(i) a recycle line for receiving at least a portion of the acid solution from the clarification means and recycling said portion to the leaching means, and
(j) means for receiving the remainder of the acid solution.

7 more elements

Dependencies are inferred from the claim text.