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 a cutting process simulation method and a system thereof which can efficiently optimize the decommissioning process of a nuclear facility, thereby saving costs and time and ensuring safety in the decommissioning process. The cutting process simulation system, according to one embodiment of the present invention, may comprise: a display unit: and a control unit which cuts a cutting target in a nuclear facility by using a design program, displays the cut shape on the display unit, and predicts the amount of secondary waste generated in the process of cutting the cutting target.

Abstract: The present invention relates to a cutting process simulation method and a system thereof which can efficiently optimize the decommissioning process of a nuclear facility, thereby saving costs and time and ensuring safety in the decommissioning process. The cutting process simulation system, according to one embodiment of the present invention, may comprise: a display unit: and a control unit which cuts a cutting target in a nuclear facility by using a design program, displays the cut shape on the display unit, and predicts the amount of secondary waste generated in the process of cutting the cutting target.

Abstract: The present invention relates to a treatment method of spent uranium catalyst, and more specifically, to a method which can considerably reduce the volume of the spent uranium catalyst to be disposed of and simultaneously minimize secondary wastes that can be generated during the process of treating the spent uranium catalyst.

Abstract: A complex electrokinetic decontamination equipment is disclosed, which removes a radionuclide from contaminated soil with a high efficiency, using a combination of a washing decontamination method performed in an electrokinetic unit using electrolyte and an electrokinetic decontamination method performed by the electrokinetic unit. pH values in an anode chamber and a cathode chamber are optimally controlled by a pH control unit, thereby reducing quantity and size of metal oxide particles. In addition, a water level of the electrolyte in the electrokinetic unit may be automatically controlled by an electrolyte supply controller.

Abstract: The present invention relates to a treatment method of spent uranium catalyst, and more specifically, to a method which can considerably reduce the volume of the spent uranium catalyst to be disposed of and simultaneously minimize secondary wastes that can be generated during the process of treating the spent uranium catalyst.

Abstract: A complex electrokinetic decontamination equipment is disclosed, which removes a radionuclide from contaminated soil with a high efficiency, using a combination of a washing decontamination method performed in an electrokinetic unit using electrolyte and an electrokinetic decontamination method performed by the electrokinetic unit. pH values in an anode chamber and a cathode chamber are optimally controlled by a pH control unit, thereby reducing quantity and size of metal oxide particles. In addition, a water level of the electrolyte in the electrokinetic unit may be automatically controlled by an electrolyte supply controller.

Abstract: Disclosed is a method and device for collecting particulate contaminants removed using a CO2 decontamination medium from an early step of a decontamination process. The device removes particulate contaminants from a contaminated subject by a decontamination stream, and simultaneously forms another stream for collecting such contaminants into a collecting filter, thus preventing such contaminants from diffusing into the atmosphere. The device forms streams between the nozzles and the surface of the contaminated subject to readily move the nozzles along the surface of the subject without frictional resistance, to reduce the sense of fatigue of the operator.

Abstract: Disclosed is a method and device for collecting particulate contaminants removed using a CO2 decontamination medium from an early step of a decontamination process. The device removes particulate contaminants from a contaminated subject by a decontamination stream, and simultaneously forms another stream for collecting such contaminants into a collecting filter, thus preventing such contaminants from diffusing into the atmosphere. The device forms streams between the nozzles and the surface of the contaminated subject to readily move the nozzles along the surface of the subject without frictional resistance, to reduce the sense of fatigue of the operator.