Abstract: A mechanical decladder for a spent nuclear fuel rod-cut includes an opening and closing unit configured to open and close an outlet of a basket into which the nuclear fuel rod-cut is loaded, a supporter on which the nuclear fuel rod-cut discharged from the outlet of the basket is seated, a hydraulic cylinder module configured to move the nuclear fuel rod-cut seated on the supporter; and a cutting module for slitting the nuclear fuel rod-cut while the nuclear fuel rod-cut is being moved by the hydraulic cylinder module. The opening and closing unit opens and closes the outlet of the basket in conjunction with a movement of the hydraulic cylinder module.

Abstract: A mechanical decladder for a spent nuclear fuel rod-cut includes an opening and closing unit configured to open and close an outlet of a basket into which the nuclear fuel rod-cut is loaded, a supporter on which the nuclear fuel rod-cut discharged from the outlet of the basket is seated, a hydraulic cylinder module configured to move the nuclear fuel rod-cut seated on the supporter; and a cutting module for slitting the nuclear fuel rod-cut while the nuclear fuel rod-cut is being moved by the hydraulic cylinder module. The opening and closing unit opens and closes the outlet of the basket in conjunction with a movement of the hydraulic cylinder module.

Abstract: There are provided an apparatus and method for separating radioactive nuclides from a waste salt and recovering a refined salt, which are able to maximize process efficiency and operating efficiency of a process of regenerating a waste salt produced during a pyrochemical process of used nuclear fuel by converting the waste salt into a thermally stable form and distilling the waste salt under a reduced pressure using a single apparatus having two top covers which are mountable to replace radioactive nuclides included in the waste salt, and highly improve applicability and utility in a remote operation facility for disposal of a radioactive waste by further simplifying operation/handling compared with conventional processes.

Abstract: The present invention relates to a method and apparatus for solidifying radioactive waste accompanying chlorine recycling or radioactive iodine removal. The present invention provide a method and apparatus for treating radioactive waste composed of volatile metal halide with high corrosiveness at a high temperature through a solidifying system including crushing, mixing/dehalogenating and sintering. In the inventive method and apparatus for solidifying radioactive waste, a dechlorination process by using a dehalogenation material is performed on highly corrosive metal salt under an oxidizing atmosphere by using a method of controlling a temperature on the surface of a reactor, and solidification is carried out by removing radioactive iodine while reusing chlorine contained in an exhaust gas. Accordingly, the generated amount of total waste can be reduced, and therefore the inventive method and apparatus can be usefully used in preparing a solidified body with high durability.

Abstract: There are provided an apparatus and method for separating radioactive nuclides from a waste salt and recovering a refined salt, which are able to maximize process efficiency and operating efficiency of a process of regenerating a waste salt produced during a pyrochemical process of used nuclear fuel by converting the waste salt into a thermally stable form and distilling the waste salt under a reduced pressure using a single apparatus having two top covers which are mountable to replace radioactive nuclides included in the waste salt, and highly improve applicability and utility in a remote operation facility for disposal of a radioactive waste by further simplifying operation/handling compared with conventional processes.

Abstract: Disclosed herein is a method of separating group II nuclides from a radioactive waste lithium chloride salt and recovering renewable lithium chloride, comprising the steps of: injecting lithium oxide into a lithium chloride salt containing group II nuclides to convert the group II nuclides into thermally-stable oxide or oxychloride; and vaporizing and condensing the lithium chloride salt under a reduced pressure condition to separate the group II nuclides and recover recyclable lithium chloride. The method is advantageous in that group II nuclides existing in the form of chloride, which is not highly thermally-stable in a lithium chloride (LiCl) to salt and is not easily solidified, can be converted into oxides or oxychlorides, which is highly thermally-stable in the lithium chloride (LiCl) salt and is easily solidified, without producing impurities.

Abstract: The present invention relates to a method and apparatus for solidifying radioactive waste accompanying chlorine recycling or radioactive iodine removal. The present invention provide a method and apparatus for treating radioactive waste composed of volatile metal halide with high corrosiveness at a high temperature through a solidifying system including crushing, mixing/dehalogenating and sintering. In the inventive method and apparatus for solidifying radioactive waste, a dechlorination process by using a dehalogenation material is performed on highly corrosive metal salt under an oxidizing atmosphere by using a method of controlling a temperature on the surface of a reactor, and solidification is carried out by removing radioactive iodine while reusing chlorine contained in an exhaust gas. Accordingly, the generated amount of total waste can be reduced, and therefore the inventive method and apparatus can be usefully used in preparing a solidified body with high durability.

Abstract: A reuse apparatus of eutectic salt waste produced in an electro refining process and a method thereof is a technology that in order to collect the eutectic salt of the eutectic salt waste, oxidizes/precipitates nuclides (rare earth and TRU) within the eutectic salt waste, an oxygen dispersing method is used to perform a layer separation into the eutectic salt layer and the precipitate layer. Then, the precipitate layer and eutectic salt layer are separated and collected, so that the eutectic salt layer is directly reused and the eutectic salt within the precipitates is reused by separating and collecting it using distillation/condensation processes. The reuse apparatus of the eutectic salt waste and a method thereof thereby increases the collecting efficiency of the eutectic salt and allows the compositions of the collected eutectic salt to have the same compositions as the eutectic salt used in the electro refining process.

Abstract: Disclosed herein are a method of recycling LiCl salt wastes comprising radionuclides and an apparatus using the same. The method includes a) solidifying a LiCl salt contained in the LiCl salt wastes and contacting the outer wall of a housing, by charging a crystallizer comprising the housing having an internal accommodating space and an air cooler in the internal accommodating space into a crystallizing furnace accommodating the LiCl salt wastes comprising the radionuclides, and by cooling the housing to a temperature of two-phase region where the liquid state and the solid state of the LiCl salt waste coexist, b) separating the crystallizer where the LiCl salt is solidified from the crystallizing furnace, c) recycling the LiCl salt by heating the separated crystallizer to melt the solidified LiCl salt.

Abstract: A reuse apparatus of eutectic salt waste produced in an electro refining process and a method thereof is a technology that in order to collect the eutectic salt of the eutectic salt waste, oxidizes/precipitates nuclides (rare earth and TRU) within the eutectic salt waste, an oxygen dispersing method is used to perform a layer separation into the eutectic salt layer and the precipitate layer. Then, the precipitate layer and eutectic salt layer are separated and collected, so that the eutectic salt layer is directly reused and the eutectic salt within the precipitates is reused by separating and collecting it using distillation/condensation processes. The reuse apparatus of the eutectic salt waste and a method thereof thereby increases the collecting efficiency of the eutectic salt and allows the compositions of the collected eutectic salt to have the same compositions as the eutectic salt used in the electro refining process.