Patent Number: 
Section: claims

1. A nuclear fuel material recovery method of recovering a nuclear fuel material comprising thorium metal by reprocessing an oxide of a nuclear fuel material comprising thorium oxide, uranium oxide, plutonium oxide, and minor actinoid oxide in a spent fuel, the method comprising, in the following order:(I) chemically reducing the thorium oxide comprised in the spent fuel in a chemical reducing agent that is a mixture of molten calcium chloride and molten metallic calcium, to produce a reaction product comprising thorium metal; and(II) electrolytically separating the thorium metal in the reaction product obtained from the chemically reducing (I), in molten salt of lithium chloride, potassium chloride, or a mixed molten salt of lithium chloride and potassium chloride. 2. The method according to claim 1, further comprising, before the chemically reducing (I):chemically reducing the uranium oxide comprised in the spent fuel in a chemical reducing agent that comprises at least one selected from the group consisting molten metallic lithium and metallic potassium to produce uranium metal. 3. The nuclear fuel material recovery method according to claim 1, wherein the chemical reduction of the thorium oxide (I) is carried out at about 850° C. to about 900° C. 4. The nuclear fuel material recovery method according to claim 2, wherein the chemical reduction of the uranium oxide is carried out at about 650° C.