| 摘要 |
<p><P>PROBLEM TO BE SOLVED: To provide a spent nuclear fuel treatment device capable of quickening a dissolving rate of a spent metal nuclear fuel, and recovering efficiently uranium or the like from the spent metal nuclear fuel. <P>SOLUTION: This spent nuclear fuel treatment device of the present invention includes a positive electrode vessel 2 and a negative electrode vessel 3 immersed in molten salts in an electrolytic bath 1, fuel pins 5 filled with the spent metal nuclear fuel in a coated tube 10 is stored in the positive electrode vessel 2, and the spent metal nuclear fuel among the fuel pins 5 is dissolved from the coated tube 10 by electrolysis. The spent nuclear fuel treatment device is further provided with a stirrer 6 for moving the fuel pins into the positive electrode vessel. <P>COPYRIGHT: (C)2007,JPO&INPIT</p> |
