REPROCESSING METHOD FOR SPENT NUCLEAR FUEL

摘要

PURPOSE: To decrease the loss of plutonium and to simplify the process of processing by adjusting the ratio of uranium weight to the plutonium weight of a nitrate water solution to a specified range. CONSTITUTION: A spent fuel is dissolved by a nitrate water solution in a dissolving vessel 1. The nitrate water solution 40 is brought into contact with an organic solution 4 in a co-decontamination extract device 3 so that uranium and plutonium shift into the organic solution 4. A scavenged organic solution 5 is brought into contact with a nitrate water solution 7 in a reverse extraction device 6 to become scavenged water solution 8 containing uranium and plutonium. The ratio of uranium to plutonium of a plutonium uranium mixed nitrate water solution 21 from an adjusting and separating device 19 is adjusted to a preset value ranging from 1 to 10. An uranium organic solution 20 is refined by an uranium refining device 13 to become high purity uranium water solution 15. The nitrate water solution 21 is refined by a mixed solution refining device 22 to become high purity mixed water solution 23. These solutions 15, 23 are respectively dried by solution driers 17, 18 and transformed to a solid.