Method of separating and recovering uranium from aluminum-clad metallic nuclear fuel
According to one aspect of the invention, a method for separating and recovering uranium from a nuclear fuel element. The method includes immersing a nuclear fuel element containing nuclear fuel and cladding in a molten metal. The nuclear fuel includes uranium. The cladding is selectively dissolved from the nuclear fuel element when immersed in the molten metal. The nuclear fuel is separated from the cladding. The method then includes loading the nuclear fuel into a permeable basket that is electrically configured as an anode of an electrolytic cell. There are also a molten salt electrolyte and a cathode in the electrolytic cell. Then, the method includes applying an electric charge across the electrolytic cell. The molten salt electrolyte selectively transfers uranium from the anode to the cathode.
1. A method for separating and recovering uranium from a nuclear fuel element, the method comprising:
(a) immersing a nuclear fuel element having a nuclear fuel and a cladding in a molten metal wherein the molten metal is molten magnesium or molten lithium, the nuclear fuel including uranium, wherein the cladding is selectively dissolved from the nuclear fuel element when contacted by the molten metal thereby leaving the nuclear fuel;
(b) loading the nuclear fuel into a permeable basket, the permeable basket is electrically configured as an anode of an electrolytic cell, the electrolytic cell having a molten salt electrolyte and a cathode; and
(c) applying an electric charge across the electrolytic cell thereby causing the molten salt electrolyte to selectively transfer uranium from the anode to the cathode.
2. The method of claim 1 wherein the nuclear fuel is a monolithic uranium-molybdenum nuclear fuel.
3. The method of claim 1 wherein the nuclear fuel is a high enriched uranium fuel.
4. The method of claim 1 wherein the nuclear fuel is a mixture of uranium and other fission products.
5. The method of claim 1 wherein the cladding contains aluminum.
6. The method of claim 1 wherein the nuclear fuel element further includes a zirconium interface layer located between the nuclear fuel and the cladding.
7. The method of claim 1 wherein the nuclear fuel remains in a metallic state following the separation of the cladding.
8. The method of claim 1 wherein the molten metal has a melting point approximately at or below the melting point of the cladding.
9. The method of claim 1 wherein the electrolyte is molten LiCl—KCl—UCl 3 .
10. The method of claim 1 wherein the uranium transferred to the cathode is free of other fuel constituents.
11. The method of claim 1 wherein the uranium transferred to the cathode is free of fission products.
12. The method of claim 1 additionally comprising the step of:
(a) drying residual molten metal from the nuclear fuel after immersing the nuclear fuel element into a molten metal.
13. The method of claim 1 additionally comprising the step of:
a) using the uranium recovered at the cathode for fabrication into a low enriched uranium nuclear fuel.
14. A method for separating and recovering uranium from a nuclear fuel element, the method comprising:
(a) immersing a nuclear fuel element having nuclear fuel, an interlayer, and a cladding in molten magnesium, the nuclear fuel being a uranium-molybdenum alloy fuel, the interlayer including zirconium, the cladding including aluminum, wherein the cladding is selectively dissolved from the nuclear fuel element when contacted by the molten magnesium thereby leaving the nuclear fuel and interlayer intact;
(b) loading the nuclear fuel and interlayer into a permeable basket, the permeable basket is electrically configured as an anode of an electrolytic cell, the electrolytic cell having a LiCl—KCl—UCl 3 electrolyte and a cathode; and
(c) applying an electric charge across the electrolytic cell thereby causing the electrolyte to selectively transfer uranium from the anode to the cathode.
15. The method of claim 1 wherein the molten magnesium has a melting point approximately equal to the melting point of the cladding.
16. The method of claim 1 additionally comprising the step of:
(e) drying residual molten magnesium from the nuclear fuel and interlayer after immersing the nuclear fuel element into the molten magnesium.
17. The method of claim 14 additionally comprising the step of:
e) using the uranium recovered at the cathode for fabrication into a low enriched uranium nuclear fuel.