A transport or storage container holding radioactive waste and a body of water is dried by the steps of first draining or pumping out the body of water and thereby leaving residual water in the container. Then at least one solid drying agent is introduced into an interior the container for removing from the interior of the container for removing the physically or chemically bonded residual water. The solid drying agent is an alkaline earth salt, particularly an alkaline earth oxide.

Proposed is a fines removal apparatus installed on a radioactive liquid waste granulator, the apparatus including: a body unit fastened to an outlet provided on the radioactive liquid waste granulator and configured to receive the granulated radioactive waste by an operation of a first opening/closing valve, the radioactive liquid waste granulator being configured to manufacture concentrated liquid waste and to manufacture granulated radioactive waste by drying the concentrated liquid waste. an air supply unit provided on one side of the body unit and configured to spray air to the supplied granulated radioactive waste at regular periods, thereby scattering and separating fines contained in the granulated radioactive waste; and a reprocessing unit provided in a vacuum state on an opposite side of the body unit and configured to allow the scattered fines to be transferred to the radioactive waste granulator along a transfer pipe by vacuum pressure.

Proposed is a fines removal apparatus installed on a radioactive liquid waste granulator, the apparatus including: a body unit fastened to an outlet provided on the radioactive liquid waste granulator and configured to receive the granulated radioactive waste by an operation of a first opening/closing valve, the radioactive liquid waste granulator being configured to manufacture concentrated liquid waste and to manufacture granulated radioactive waste by drying the concentrated liquid waste. an air supply unit provided on one side of the body unit and configured to spray air to the supplied granulated radioactive waste at regular periods, thereby scattering and separating fines contained in the granulated radioactive waste; and a reprocessing unit provided in a vacuum state on an opposite side of the body unit and configured to allow the scattered fines to be transferred to the radioactive waste granulator along a transfer pipe by vacuum pressure.

A method for the radiological characterisation of the radiation listing of mercury, comprising the Steps: a. preparing a predefined quantity of mercury, b. evaporating at least one fraction of the prepared mercury, and c. the radioactive γ-radiation emitted by the gaseous mercury.

A method for the radiological characterisation of the radiation listing of mercury, comprising the Steps: a. preparing a predefined quantity of mercury, b. evaporating at least one fraction of the prepared mercury, and c. the radioactive γ-radiation emitted by the gaseous mercury.

A bath electrical heating device for deactivation designed to provide heating of bath deactivation and the deactivating solution in it before deactivation of reactor facility equipment and ensuring the removal of excess heat in the process of deactivation. The invention improves reliability, reduces the material consumption of the device and simplifies the structure installation and repair. The device performs at least from three heat insulation blocks in the form of coaxial metal screens, installed with an air gap from the heater. The heater with current leads is made in hermetic perform, each heat insulation blocks supplemented with an air-gap coaxial metal protective casing. The air gap of which in the upper part is covered with a cap with a visor whose diameter exceeds the external diameter of the protective casing, wherein solid cover of the upper protective casing install a sealed coupling.

The present invention relates to a method of separating and removing a radioactive nuclide, particularly, C-14 and tritium from a radioactive waste resin, and an equipment therefor. The method of treating a radioactive waste resin of the present invention includes recycling of condensate water from which a C-14 radionuclide in the condensate water is removed, into a treatment part for a radioactive waste resin.

The present invention relates to a method of separating and removing a radioactive nuclide, particularly, C-14 and tritium from a radioactive waste resin, and an equipment therefor. The method of treating a radioactive waste resin of the present invention includes recycling of condensate water from which a C-14 radionuclide in the condensate water is removed, into a treatment part for a radioactive waste resin.

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.

Disclosed are a method and a device for recovering uranium (U) using a process for chemically treating washing wastewater of a uranium hexafluoride (UF6) cylinder. The method and the device are provided to separate uranium (U) from the wastewater released during a process of washing the uranium hexafluoride (UF6) cylinder and to release a filtrate that satisfies atomic energy licensing standards and environmental regulation standards using evaporation and condensation. Accordingly, an independent technology and process for treating the wastewater released during the process of washing the uranium hexafluoride (UF6) cylinder are ensured, which provides easier maintenance and greatly reduces costs compared to the purchase and operation of apparatuses manufactured by foreign makers.