Method for reprocessing spent nuclear fuel

Chemistry of inorganic compounds – Treating mixture to obtain metal containing compound – Radioactive metal

Reexamination Certificate

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C423S001000, C423S251000, C423S253000

Reexamination Certificate

active

10761432

ABSTRACT:
It is an object to increase a reprocessing speed of spent nuclear fuel and to obtain uranium having a high purity and a plutonium mixture reusable as it is at a low cost through a simple procedure.The spent nuclear fuel1is subjected to fluorination using fluorine2in a fluorination step3, and as a result, uranium, a mixture of uranium and plutonium and a fission product are separated and recovered independently of one another. The plutonium fluoride volatilized in the fluorination is recovered along with a fixing agent and then passed through an oxidative conversion step8, thereby recovering a mixture of uranium and plutonium oxides9. Since the uranium can be recovered in a high purity, it is managed very easily when reused or saved. Further, since the uranium and plutonium are recovered as a mixture thereof, fuel reproduction cost is decreased and prevention of proliferation is strengthened.

REFERENCES:
patent: 3708568 (1973-01-01), Golliher et al.
patent: 3753920 (1973-08-01), Anastasia et al.
patent: 2002/0122762 (2002-09-01), Fukasawa et al.
patent: 2004/0201002 (2004-10-01), Caranoni et al.
patent: P2000-284089 (2000-10-01), None
patent: P2002-257980 (2002-09-01), None
Nuclear Chemical Engineering, Second Edition, edited by M. Benedict, et al., translated by Ryohei Kiyose, Chapter 10, pp. 457-564.
Aoji, T., et al. “Dry Reprocessing Process, Development History and Current Status” Nuclear power industry (Gensiryoku-Kogyo), issued by the Nikkan Kogyo Shinbun-sha (daily industrial newspaper office), Nov. 19, 2002, vol. 17, No. 3.

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