Abstract: A spent nuclear fuel is reprocessed by dissolving a spent nuclear fuel in an aqueous nitric acid solution and separating and recovering nuclides contained in the resulting fuel solution by solvent extraction. A spent nuclear fuel reprocessing method includes: an electrolytic valence adjustment step in which nuclides contained in the fuel solution is electrolytically reduced without removing fission products or minor actinides until valence of plutonium is at a level at which solvent extraction efficiency is low by using the valence of plutonium contained in the fuel solution as a parameter; and a nuclide separation step in which, by using an extraction solvent which extracts uranium contained in the fuel solution, uranium is distributed from the fuel solution subjected to the electrolytic valence adjustment step to the extraction solvent.

Abstract: An object of the present invention is to provide a method of producing metal zirconium, the method having a fewer steps and a smaller amount of secondary wastes generated, wherein the metal zirconium is obtained from a zirconium compound containing hafnium. A method of producing metal zirconium according to the present invention includes: a separation step of separating a hafnium oxychloride from a first substance containing a zirconium oxychloride and a hafnium oxychloride to obtain a second substance having a higher content of the zirconium oxychloride; a calcination step of calcining the second substance to obtain a third substance containing at least any of a zirconium oxychloride and a zirconium oxide; and a direct reduction step of holding the third substance in a molten salt with the third substance brought into contact with a cathode and applying a voltage between the cathode and an anode to directly reduce the third substance to obtain metal zirconium.

Abstract: An object of the present invention is to provide a method of producing metal zirconium, the method having a fewer steps and a smaller amount of secondary wastes generated, wherein the metal zirconium is obtained from a zirconium compound containing hafnium. A method of producing metal zirconium according to the present invention includes: a separation step of separating a hafnium oxychloride from a first substance containing a zirconium oxychloride and a hafnium oxychloride to obtain a second substance having a higher content of the zirconium oxychloride; a calcination step of calcining the second substance to obtain a third substance containing at least any of a zirconium oxychloride and a zirconium oxide; and a direct reduction step of holding the third substance in a molten salt with the third substance brought into contact with a cathode and applying a voltage between the cathode and an anode to directly reduce the third substance to obtain metal zirconium.

Abstract: A spent nuclear fuel is reprocessed by dissolving a spent nuclear fuel in an aqueous nitric acid solution and separating and recovering nuclides contained in the resulting fuel solution by solvent extraction. A spent nuclear fuel reprocessing method includes: an electrolytic valence adjustment step in which nuclides contained in the fuel solution is electrolytically reduced without removing fission products or minor actinides until valence of plutonium is at a level at which solvent extraction efficiency is low by using the valence of plutonium contained in the fuel solution as a parameter; and a nuclide separation step in which, by using an extraction solvent which extracts uranium contained in the fuel solution, uranium is distributed from the fuel solution subjected to the electrolytic valence adjustment step to the extraction solvent.

Abstract: A spent fuel reprocessing method has a dissolution step of dissolving the spent fuel in nitric acid solution, an electrolysis/valence adjustment step of reducing Pu to trivalent, maintaining the pentavalent of Np, a uranium extraction step of collecting UO2 by bringing the fuel into contact with organic solvent and extracting hexavalent U by means of an extraction agent, an oxalic acid precipitation step of causing MA and the fissure products remaining in the nitric acid solution to precipitate together as oxalic acid precipitate, a chlorination step of converting the oxalic acid precipitate into chlorides by adding hydrochloric acid to the oxalic acid precipitate, a dehydration step of synthetically producing anhydrous chlorides by dehydrating the chlorides in a flow of Ar gas, and a molten salt electrolysis step of dissolving the anhydrous chlorides into molten salt and collecting U, Pu and MA at the cathode by electrolysis.