Patent Number: 
Section: claims

1. A method for acquiring uranium and/or fission products from irradiated nuclear fuel, the method comprising:exposing the irradiated nuclear fuel to an aqueous solution to form a mixture comprising a solid phase and a liquid phase while maintaining the pH of the liquid phase at from greater than 7 to less than 10;separating the solid phase from the liquid phase; andprocessing the liquid phase to acquire at least a portion of one or both of the uranium and/or the fission products. 2. The method of claim 1 wherein the aqueous solution comprises one or more of ammonium, carbonate, and peroxide. 3. The method of claim 1 wherein the aqueous solution comprises an ammonium-carbonate solution. 4. The method of claim 1 wherein the aqueous solution comprises carbonate and peroxide. 5. The method of claim 1 wherein the processing comprises exposing at least a portion of the liquid phase to an adsorbent to remove at least some of the solute from the liquid phase and form an effluent containing the portion of one or both of the uranium and/or the fission products. 6. The method of claim 5 wherein the adsorbent comprises an ion exchange resin. 7. The method of claim 5 further comprising exposing the effluent to an extraction solution to purify the portion of one or both of the uranium and/or the fission products. 8. The method of claim 1 wherein the irradiated nuclear fuel further comprises cladding. 9. The method of claim 1 wherein the irradiated nuclear fuel are targets within regulated containers. 10. The method of claim 1 further comprising exposing the targets to peroxide. 11. The method of claim 1 further comprising exposing the targets to carbonate. 12. The method of claim 1 further comprising exposing the targets to carbonate and peroxide. 13. The method of claim 1 wherein the processing the liquid phase can comprise combining the liquid phase with a hydroxide solution to form another mixture. 14. The method of claim 13 wherein the hydroxide solution comprises Ba. 15. The method of claim 13 wherein the processing the liquid phase can further comprise warming the other mixture while maintaining ammonium carbonate in the other mixture. 16. The method of claim 13 wherein the processing the liquid phase can further comprise exposing the other mixture to an adsorbent to acquire the portion of one or both of the uranium and/or the fission products.