Irradiated fuel reprocessing

Claim 2

In a process for treating irradiated nuclear fuel to recover uranium and at least one transuranic isotope selected from the group consisting of neptunium and plutonium so that said uranium and said at least one transuranic isotope are substantially free of fission products which comprises dissolving said fuel in a strong mineral acid and forming an aqueous dissolved nuclear fuel solution and subsequentially treating said dissolved solution to separate said uranium and said at least one transuranic isotope therefrom substantially free of said fission products, the improvement comprising adding to said solution prior to treatment for separation of said uranium and said transuranic isotope a sufficient amount of an additive of a non-radioactive [stable ] metallic complex in which the metallic component is selected from the group consisting of niobium, tantalum and combinations thereof and said amount is sufficient to alter the decontamination factor exhibited by radioactive niobium in said solution.

Claim 3

The process of claim 1 in which the additive is a niobium complex in a mineral acid.

Claim 4

The process of claim 2 in which the acid is nitric acid.

Claim 5

The process of claim 2 in which the additive is a niobium proxide complex.

Claim 6

The process of claim 2 in which the additive is a niobium oxalate complex.

Claim 7

The process of claim 2 in which the additive is a niobium tartrate complex.

Claim 8

The process of claim 1 in which the additive is a tantalum proxide complex.

Claim 9

The process of claim 1 in which the additive is a tantalum oxalate complex.

Claim 10

The process of claim 1 in which the additive is a tantalum tartrate complex.

Claim 11

The process of claim 1 in which the additive is present in an amount of about 10 - 6 to about 10 - 3 moles per liter of said solution.

Claim 12

The process of claim 1 in which an oxidant is added to said solution with said stable metallic complex.

Claim 13

The process of claim 1 in which the oxidant is selected from the group consisting of potassium bromate and potassium permanganate.

Claim 14

A process for treating irradiated nuclear fuel contained in clad rods to recover separately uranium, neptunium, and plutonium therefrom substantially free of fission products, said process comprising the steps of a. perforating the clad of the rods, b. contacting the perforated rods with a strong mineral acid to dissolve the nuclear fuel and form an acid dissolver solution, c. adding to said dissolver solution an additive of a nonradioactive metallic complex in an amount sufficient to alter the decontamination factor of radioactive niobium in said dissolver solution, said complex having the metallic component selected from the group consisting of niobium, tantalum and combinations thereof, d. contacting said dissolver solution with an organic solvent to separate uranium, plutonium and neptunium into the organic solvent from said dissolver solution and leave an aqueous solvent extraction raffinate containing fission products, e. contacting the organic solvent with a dilute mineral acid to strip the uranium, plutonium and neptunium from the organic solvent and from an aqueous extraction product, f. adjusting the valence of plutonium and neptunium by contacting said aqueous solvent extraction product with a reductant, g. concentrating said aqueous extraction product, g. cooling said concentrated aqueous solvent extraction product, i. contacting said concentrated aqueous solvent extraction product with an anion exchange resin so that plutonium in the +4 valence is extracted by the resin, leaving a first aqueous anion exchange raffinate containing neptunium and uranium, j. adjusting the valence of the neptunium in said first aqueous anion exchange raffinate with a reductant, k. contacting said first aqueous anion exchange raffinate with an anion exchange resin to extract the neptunium therefrom, and giving a second aqueous anion exchange raffinate, l. dehydrating said second aqueous anion exchange raffinate to an anhydrous solid of uranium oxide, and m. fluorinating the anhydrous solid to give uranium hexafluoride.

Claim 15

A process for treating irradiated nuclear fuel contained in clad rods to recover separately uranium, neptunium, and plutonium therefrom substantially free of fission products, said process comprising the steps of a. perforating the clad of the rods, b. contacting the perforated rods with a strong mineral acid to dissolve the nuclear fuel and form an acid dissolver solution, c. adding to said dissolver solution an additive of a nonradioactive metallic complex in an amount sufficient to alter the decontamination factor of radioactive niobium in said dissolver solution, said complex having the metallic component selected from the group consisting of niobium, tantalum and combinations thereof, d. contacting said dissolver solution with an organic solvent to separate uranium, plutonium and neptunium into the organic solvent from said dissolver solution and leave an aqueous solvent extraction raffinate containing fission products, e. contacting the organic solvent with a dilute mineral acid to strip the uranium, plutonium and neptunium from the organic solvent and from an aqueous extraction product, f. adjusting the valence of plutonium and neptunium by contacting said aqueous solvent extraction product with a reductant, g. concentrating said aqueous extraction product, g. cooling said concentrated aqueous solvent extraction product, i. contacting said concentrated aqueous solvent extraction product with an anion exchange resin so that plutonium in the +4 valence is extracted by the resin, leaving a first aqueous anion exchange raffinate containing neptunium and uranium, j. adjusting the valence of the neptunium in said first aqueous anion exchange raffinate with a reductant, k. contacting said first aqueous anion exchange raffinate with an anion exchange resin to extract the neptunium therefrom, and giving a second aqueous anion exchange raffinate, l. dehydrating said second aqueous anion exchange raffinate to an anhydrous solid of uranium oxide, and m. fluorinating the anhydrous solid to give uranium hexafluoride.

Claim 16

The process of claim 13 in which the additive is a niobium complex in a mineral acid.

Claim 17

The process of claim 14 in which the acid is nitric acid.

Claim 18

The process of claim 14 in which the additive is a niobium peroxide complex.

Claim 19

The process of claim 14 in which the additive is a niobium oxalate complex.

Claim 20

The process of claim 14 in which the additive is a niobium tartarate complex.

Claim 21

The process of claim 1 in which the additive is a tantalum peroxide complex.

Claim 22

The process of claim 13 in which the additive is a tantalum oxalate complex.

Claim 23

The process of claim 13 in which the additive is a tantalum tartrate complex.

Claim 24

The process of claim 13 in which the additive is present in an amount of about 10.sup. -6 to about 10.sup. -3 moles per liter of said solution.

Claim 25

The process of claim 13 in which an oxidant is added to said solution with said stable metallic complex.

Claim 26

The process of claim 13 in which the oxidant is selected from the group consisting of potassium bromate and potassium permanganate.