Method of reprocessing spent nuclear fuel
View Patent ↗Most part of an amount of uranium contained in the spent nuclear fuel is removed by making fluorine or a fluorochemical act on the spent nuclear fuel to convert the uranium into UF 6 , and the uranium is purified through a simple method of distilling the UF 6 together with a absorbent. After removing the most part of the amount of uranium, the remaining nuclear fuel material is dissolved and then transferred to an extraction process to recover plutonium. By doing so, a small sized dry process can be employed as a uranium purification process. Since the nuclear fuel material is dissolved and extracted after removing most part of an amount of uranium, a volume of processing solution can be reduced and the machine installation scale can be made small. Accordingly, the reprocessing facility can be extremely downsized.
1. A method of reprocessing spent nuclear fuel, comprising:
vaporizing and removing part of an amount of uranium contained in the spent nuclear fuel, thereby to separate the part of the uranium amount from the spent nuclear fuel, by making fluorine or a fluorochemical act on the spent nuclear fuel, wherein an amount of uranium separation is adjusted so that a weight ratio of plutonium to uranium contained in remaining spent nuclear fuel that remains after said vaporizing and removing falls within a range of 1:1 to 1:10; and then
performing solvent extraction of a mixture of uranium, plutonium and other nuclides contained in the remaining spent nuclear fuel to remove the other nuclides from the mixture.
2. A method of reprocessing spent nuclear fuel according to claim 1 , wherein the uranium removed from the spent nuclear fuel by making fluorine or a fluorochemical act on the spent nuclear fuel is purified in a form of UF6.
3. A method of reprocessing spent nuclear fuel, comprising:
removing part of an amount of uranium contained in the spent nuclear fuel, thereby to separate the part of the uranium amount from the spent nuclear fuel, by making fluorine or a fluorochemical act on the spent nuclear fuel, wherein an amount of uranium separation is adjusted so that a weight ratio of plutonium to uranium contained in remaining spent nuclear fuel that remains after removing the part of the uranium amount falls within a range of 1:1 to 1:10;
extracting for transferring plutonium and uranium to an organic solvent by making the organic solvent act on an aqueous liquid containing the remaining spent nuclear fuel obtained from said spent nuclear fuel; and
inverse extracting for transferring said plutonium and uranium from said organic solvent to an aqueous liquid.
4. A method of reprocessing spent nuclear fuel according to claim 3 , wherein said removing part of an amount of uranium contained in the spent nuclear fuel is performed before a process for dissolving the remaining spent nuclear fuel.
5. A method of reprocessing spent nuclear fuel according to claim 3 , wherein the uranium removed from the spent nuclear fuel by making fluorine or a fluorochemical act on the spent nuclear fuel is purified in a form of UF6.
6. A method of reprocessing spent nuclear fuel, comprising
vaporizing and removing part of an amount of uranium contained in the spent nuclear fuel thereby to adjust a weight ratio of uranium to plutonium, by making fluorine or fluorochemical act on spent nuclear fuel; and then
solvent extracting a mixture of uranium, plutonium and other nuclides contained in a remainder of the spent nuclear fuel after the vaporizing and removing of the part of the uranium amount to remove said other nuclides from said mixture, thereby to separate uranium and plutonium from said other nuclides.
7. A method of reprocessing spent nuclear fuel, comprising
removing part of an amount of uranium contained in the spent nuclear fuel thereby to adjust a weight ratio of uranium to plutonium so that a part of the uranium amount remains in the spent nuclear fuel, by making fluorine or a fluorochemical act on the spent nuclear fuel;
extracting for transferring plutonium and uranium to an organic solvent by making the organic solvent act on an aqueous liquid containing a nuclear fuel material obtained from said spent nuclear fuel from which the part of the uranium amount is removed; and
inverse extracting for transferring said plutonium and uranium from said organic solvent to an aqueous liquid.