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 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: [A] method and an apparatus for the treatment of waste ion exchange resins containing radionuclides, and further relating to a method for the treatment of waste ion exchange resins containing radionuclides by the stepwise heat treatment and an apparatus to accomplish the method.

Abstract: Provided is a method of separating carbon and oxygen isotopes by using a laser. In one preferred embodiment, the method includes performing a photolysis process on formaldehyde including a carbon or oxygen isotope by irradiation with ultraviolet light having a wavelength ranging from 340 nm to 360 nm to generate carbon monoxide having a carbon or oxygen isotope enriched therein and hydrogen, performing a catalytic reaction on the carbon monoxide having a carbon or oxygen isotope enriched therein and the hydrogen to synthesize carbon dioxide (CO2) and water (H2O) having a carbon or oxygen isotope enriched therein, and cooling the H2O to recover CO2 having a carbon isotope enriched therein or H2O having an oxygen isotope enriched therein.

Abstract: A method and an apparatus for the treatment of waste ion exchange resins containing radionuclides, and the present invention relates to a method for the treatment of waste ion exchange resins containing radionuclides by the stepwise heat treatment and an apparatus to accomplish the said method.

Abstract: Provided are a separation and recovery device for a liquid waste including a radionuclide, and a separation and recovery method using the same. Specifically, the present disclosure relates to a separation and recovery device that may effectively separate a liquid waste, such as a waste detergent including a radionuclide, and simultaneously, may prevent the release of tritium and radiocarbon to the outside, and a separation and recovery method using the same.

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: Provided is a method of separating carbon and oxygen isotopes by using a laser. In one preferred embodiment, the method includes performing a photolysis process on formaldehyde including a carbon or oxygen isotope by irradiation with ultraviolet light having a wavelength ranging from 340 nm to 360 nm to generate carbon monoxide having a carbon or oxygen isotope enriched therein and hydrogen, performing a catalytic reaction on the carbon monoxide having a carbon or oxygen isotope enriched therein and the hydrogen to synthesize carbon dioxide (CO2) and water (H2O) having a carbon or oxygen isotope enriched therein, and cooling the H2O to recover CO2 having a carbon isotope enriched therein or H2O having an oxygen isotope enriched therein.

Abstract: Provided are a separation and recovery device for a liquid waste including a radionuclide, and a separation and recovery method using the same. Specifically, the present disclosure relates to a separation and recovery device that may effectively separate a liquid waste, such as a waste detergent including a radionuclide, and simultaneously, may prevent the release of tritium and radiocarbon to the outside, and a separation and recovery method using the same.

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.