Patent Number: 
Section: claims

1. An electrolytic apparatus for use in an oxide electrowinning method, said apparatus comprising:an annular electrolytic vessel made of a metallic material and having an annular space with a bottom formed therein and an upper portion;a high frequency induction coil for heating a substance to be processed in said electrolytic vessel;an annular anode installed at the bottom of the annular space formed in the annular electrolytic vessel;rod-shaped anodes and rod-shaped cathodes installed in the upper portion along the axial direction in the annular space and arranged in parallel, the rod-shaped anodes and the annular anode being arranged vertically;a first electrolysis controller connected between the rod-shaped cathodes and the annular anode, anda second electrolysis controller connected between the rod-shaped cathodes and the rod-shaped anodes,wherein one of a parallel pair of the rod-shaped anodes and the rod-shaped cathodes arranged in parallel or and a vertical pair of the annular anode and the rod-shaped cathodes arranged vertically is used for main electrolysis and the other of the pairs is used for auxiliary electrolysis. 2. An electrolytic apparatus for use in an oxide electrowinning method according to claim 1, further comprising a rotational driving mechanism, wherein the rod-shaped cathodes are supported rotationally and are rotated by the rotational driving mechanism. 3. A spent nuclear fuel reprocessing method with an oxide electrowinning method by using the electrolytic apparatus according to claim 1, wherein the oxide electrowinning method comprises:a simultaneous electrolytic step, including dissolving uranium oxide contained in spent nuclear fuel into a molten salt in the annular electrolytic vessel due to an anodic oxidation reaction, and simultaneously recovering uranium oxide by depositing uranium oxide on the surface of the cathodes due to cathodic reduction;a dissolution step by chlorination in which the electrolytic step is stopped, including dissolving uranium oxide, plutonium oxide and other elements remaining in the spent nuclear fuel into the molten salt by blowing chlorine gas into the molten salt to convert the uranium oxide, the plutonium oxide and other elements remaining in the spent nuclear fuel to chlorides thereof; anda MOX recovery step, including performing electrolysis between the anodes and the rod-shaped cathodes installed in the upper portion of the annular space, and recovering oxides of uranium and plutonium by deposition of the oxides in a mixed state on the surface of the cathodes, after the entire spent nuclear fuel has been dissolved into the molten salt;wherein in the simultaneous electrolytic step, the vertical pair of the annular anode and the rod-shaped cathodes is used for main electrolysis in which uranium oxide is dissolved and deposited by electrochemical reaction and the parallel pair of the rod-shaped anodes and the rod-shaped cathodes is used for auxiliary electrolysis for suppressing ununiform uranium oxide electrodeposition, andwherein in the MOX recovery step, the parallel pair of the rod-shaped anodes and the rod-shaped cathodes is used for main electrolysis in which the MOX is deposited, and the vertical pair of the annular anode and the rod-shaped cathodes is used for auxiliary electrolysis for dissolving any electrodeposit which has fallen down from the cathodes. 4. A spent nuclear fuel reprocessing method with an oxide electrowinning method by using the electrolytic apparatus according to claim 2, wherein the oxide electrowinning method comprises:a simultaneous electrolytic step, including dissolving uranium oxide contained in spent nuclear fuel into a molten salt in the annular electrolytic vessel due to an anodic oxidation reaction, and simultaneously recovering uranium oxide by depositing uranium oxide on the surface of the cathodes due to cathodic reduction;a dissolution step by chlorination in which the electrolytic step is stopped, including dissolving uranium oxide, plutonium oxide and other elements remaining in the spent nuclear fuel into the molten salt by blowing chlorine gas into the molten salt to convert the uranium oxide, the plutonium oxide and other elements remaining in the spent nuclear fuel to chlorides thereof; anda MOX recovery step, including performing electrolysis between the anodes and the rod-shaped cathodes installed in the upper portion of the annular space, and recovering oxides of uranium and plutonium by deposition of the oxides in a mixed state on the surface of the cathodes, after the entire spent nuclear fuel has been dissolved into the molten salt;wherein in the simultaneous electrolytic step, the vertical pair of the annular anode and the rod-shaped cathodes is used for main electrolysis in which uranium oxide is dissolved and deposited by electrochemical reaction and the parallel pair of the rod-shaped anodes and the rod-shaped cathodes is used for auxiliary electrolysis for suppressing ununiform uranium oxide electrodeposition, andwherein in the MOX recovery step, the parallel pair of the rod-shaped anodes and the rod-shaped cathodes is used for main electrolysis in which the MOX is deposited, and the vertical pair of the annular anode and the rod-shaped cathodes is used for auxiliary electrolysis for dissolving any electrodeposit which has fallen down from the cathodes.