Abstract: The present disclosure provides a solidifying method of a radionuclide. The solidifying method of the radionuclide includes operations of: providing a low melting point glass including Bi2O3, B2O3, ZnO and SiO2; providing a glass mixture mixing a mixture to be treated containing a hydroxide of radionuclide and BaSO4 and the low melting point glass; and heating the glass mixture.

Abstract: The present disclosure provides a solidifying method of a radionuclide. The solidifying method of the radionuclide includes operations of: providing a low melting point glass including Bi2O3, B2O3, ZnO and SiO2; providing a glass mixture mixing a mixture to be treated containing a hydroxide of radionuclide and BaSO4 and the low melting point glass; and heating the glass mixture.

Abstract: The present invention relates to an apparatus for treating a spent ion exchange resin, the apparatus including: a graphite reactor for receiving a spent ion exchange resin including a radionuclide-containing ion exchange group therein; a graphite heater for heating the spent ion exchange resin; an inert gas injection tube for injecting an inert gas into the graphite reactor for drying and carbonizing the spent ion exchange resin; and a halogenation gas injection tube for injecting a halogen-containing gas or a halogenation compound gas into the graphite reactor for halogenation of a compound derived from the radionuclide-containing ion exchange group, and to a method for treating a spent ion exchange resin, the method including steps of (A) drying a spent ion exchange resin including a radionuclide-containing ion exchange group; (B) producing a compound derived from the radionuclide-containing ion exchange group by separating the radionuclide-containing ion exchange group from the dried spent ion exchange res

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: 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: 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: 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.