Larry Ray Short

US Patent:

42306728, Oct 28, 1980

Filed:

Dec 24, 1978

Appl. No.:

5/972525

Inventors:

Larry A. Divins - Wilmington NC
Larry E. Short - Wilmington NC

Assignee:

General Electric Company - San Jose CA

International Classification:

B01J 100
G21F 930

US Classification:

422159

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.

US Patent:

41772415, Dec 4, 1979

Filed:

Sep 8, 1977

Appl. No.:

5/831689

Inventors:

Larry A. Divins - Wilmington NC
Larry E. Short - Wilmington NC

Assignee:

General Electric Company - San Jose CA

International Classification:

G21F 930

US Classification:

423 20

Abstract:

A 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.