Abstract: The present disclosure relates to a method of removing a radioactive structure from a nuclear power plant. The method includes flattening at least a portion of an outer surface of a drilling portion of a wall of a nuclear reactor vessel when the portion of the outer surface is uneven, wherein the radioactive structure is buried in the wall and the drilling portion is adjacent to the radioactive structure, installing a drilling device in the flattened drilling portion and performing a drilling operation, extracting the radioactive structure from the wall, and cutting the extracted radioactive structure and storing pieces of the cut radioactive structure in a shielding container.

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 a method of separating fine particles in soil using cationic magnetic nanoparticles, and more particularly, to a method of separating fine particles (clay, silt, etc.) that have adsorbed contaminants such as heavy metals or radioactive nuclides in soil using cationic magnetic nanoparticles. According to the present invention, contaminants such as heavy metals or radioactive nuclides selectively or irreversibly adsorbed to fine particles (clay, silt, etc.) in soil may be economically and efficiently separated. Therefore, the present invention may be effectively used to restore soil in residential areas that are contaminated with radioactive nuclides in serious accidents such as the Fukushima Daiichi nuclear disaster as well as facility sites contaminated with heavy metals or radioactive nuclides.

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 relates to a method of removing a nuclear power plant activation structure. Specifically, an embodiment of the present disclosure may provide a method of removing a nuclear power plant activation structure including flattening at least a portion of a wall surface of a peripheral portion of a wall of a nuclear reactor, the wall including a buried portion in which a nuclear power plant activation structure is buried and the peripheral portion circumferentially surrounding the buried portion; installing a drilling device in the flattened peripheral portion and performing a drilling operation; removing the nuclear power plant activation structure from the buried portion; and cutting the removed nuclear power plant activation structure and storing pieces of the cut nuclear power plant activation structure in a shielding container.

Abstract: The present invention relates to a method for removing cesium in a clay mineral using hydrogen peroxide. According to the present invention, cesium in a clay mineral is removed using hydrogen peroxide, which serves to induce interlayer expansion of the clay mineral to allow a cation to easily enter an interlayer of the clay mineral, and thus cesium desorption efficiency can be further improved. Also, the method according to the present invention can be efficiently used to restore soil in residential areas widely contaminated with a radionuclide when a major accident such as Fukushima nuclear accident occurs as well as various sites of atomic energy facilities contaminated with a radionuclide. Also, since radiation-contaminated soil is treated with only hydrogen peroxide and cations, secondary environmental pollution caused by wastes can be significantly reduce and the waste disposing cost can also be saved.

Abstract: There is provided a method for decommissioning plan of nuclear facility includes receiving a plurality of decommissioning related information data, and determining whether error data is included in the plurality of decommissioning related information data based on a database which contains characteristic information and decommissioning plan information of a plurality of nuclear facilities. The method further includes analyzing a state of a decommissioning target facility by identifying the decommissioning target facility based on the plurality of decommissioning related information data and the database, wherein when the error data is included in the plurality of decommissioning related information data, said analyzing is performed by identifying the decommissioning target facility based on the plurality of decommissioning related information data from which the error data is excluded and the database.

Abstract: A radioactive waste container, for storing and transporting a radioactive waste, includes a container body, a cover and a water drain unit. The cover is fastened to the container body. The water drain unit is provided at the container body without protruding to an outside of the container body and configured to selectively drain water in the container body.

Abstract: A volume reduction treatment method able to reduce the volume of the final disposal waste of a spent uranium catalyst. As a result, the disposal cost of the spent uranium catalyst is able to be reduced and the utilization of waste repositories are able to be improved.

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: A radioactive waste container, for storing and transporting a radioactive waste, includes a container body, a cover and a water drain unit. The cover is fastened to the container body. The water drain unit is provided at the container body without protruding to an outside of the container body and configured to selectively drain water in the container body.

Abstract: The present invention relates to a method for removing cesium in a clay mineral using hydrogen peroxide. According to the present invention, cesium in a clay mineral is removed using hydrogen peroxide, which serves to induce interlayer expansion of the clay mineral to allow a cation to easily enter an interlayer of the clay mineral, and thus cesium desorption efficiency can be further improved. Also, the method according to the present invention can be efficiently used to restore soil in residential areas widely contaminated with a radionuclide when a major accident such as Fukushima nuclear accident occurs as well as various sites of atomic energy facilities contaminated with a radionuclide. Also, since radiation-contaminated soil is treated with only hydrogen peroxide and cations, secondary environmental pollution caused by wastes can be significantly reduce and the waste disposing cost can also be saved.

Abstract: The present invention relates to a volume reduction treatment method of a spent uranium catalyst. According to the volume reduction treatment method of a spent uranium catalyst of the present invention, the disposal cost of the spent uranium catalyst can be reduced and the utilization of the repository can be improved since the method can significantly reduce the volume of the final disposal waste of the spent uranium catalyst.

Abstract: Provided are a biomineralogical method for removing cesium ions. The method for removing cesium ions, the method comprising: adding metal-reducing bacteria, an iron source, and a sulfur source into a solution containing the cesium ions to convert the cesium ions into a solid mineral incorporating cesium. The method for removing cesium ions according to the present invention has advantages in that the cesium ions may be removed with high efficiency and small volume even in the case in which competing ions are present at a high concentration like sea water.