The present invention provides a system for evaporating a radioactive fluid, a method for the synthesis of a radiolabelled compound including this system, and a cassette for the synthesis of a radiolabelled compound comprising this system. The present invention provides advantages over known methods for evaporation of a radioactive fluid as it reduces drastically the amount of radioactive gaseous chemicals that are released in the hot cell. It is gentler and more secure compared to the known process and provides access to radiosyntheic processes that may not been acceptable for safety reasons related to release of volatile radioactive gases during evaporation. In addition, the process yields are higher because the radioactive volatiles are labelled intermediate species.

The invention relates to the field of environmental protection, more specifically to the field of processing radioactive waste, and can he used for the safe and effective handling of a large quantity of liquid radioactive waste of various activity levels that has been formed as the result of decontaminating protective equipment of boxes and chambers, and makes it possible to decrease the volume of stored waste by solidifying same and incorporating same into a ceramic matrix. For this purpose, radioactive solutions after decontamination of surfaces of protective equipment are evaporated as alkaline and acidic solutions containing sodium hydroxide, potassium permanganate, oxalic acid, and nitric acid until a solid residue forms, and are calcined, and the calcinate is mixed with components of a fusion mixture containing oxides of titanium, calcium, iron (III), zirconium, and manganese (IV) and aluminum in a specified ratio, and fused.

The invention relates to the field of environmental protection, more specifically to the field of processing radioactive waste, and can he used for the safe and effective handling of a large quantity of liquid radioactive waste of various activity levels that has been formed as the result of decontaminating protective equipment of boxes and chambers, and makes it possible to decrease the volume of stored waste by solidifying same and incorporating same into a ceramic matrix. For this purpose, radioactive solutions after decontamination of surfaces of protective equipment are evaporated as alkaline and acidic solutions containing sodium hydroxide, potassium permanganate, oxalic acid, and nitric acid until a solid residue forms, and are calcined, and the calcinate is mixed with components of a fusion mixture containing oxides of titanium, calcium, iron (III), zirconium, and manganese (IV) and aluminum in a specified ratio, and fused.

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.

Mercury that may be contaminated radioactively is converted with radionuclides of other elements to a gaseous state of aggregation, which increases the distance between the mercury atoms and reduces the shielding effect of the mercury with respect to the radionuclides of other elements contained in the mercury. The method disclosed, enables the radiological characterisation of the radiation listing of mercury, without prior processing, in particular homogenization, of the sample being necessary. In particular, the method enables continuous measurement of the entire mass to be characterized and includes preparing a predefined quantity of mercury, evaporating at least one fraction of the prepared mercury, and measuring the radioactive ?-radiation emitted by the gaseous mercury.

Mercury that may be contaminated radioactively is converted with radionuclides of other elements to a gaseous state of aggregation, which increases the distance between the mercury atoms and reduces the shielding effect of the mercury with respect to the radionuclides of other elements contained in the mercury. The method disclosed, enables the radiological characterisation of the radiation listing of mercury, without prior processing, in particular homogenization, of the sample being necessary. In particular, the method enables continuous measurement of the entire mass to be characterized and includes preparing a predefined quantity of mercury, evaporating at least one fraction of the prepared mercury, and measuring the radioactive ?-radiation emitted by the gaseous mercury.

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.

[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.

[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.