A system and method of clearing radioactive contamination from a surface is provided by means of a handheld device and a method of using the handheld device. The handheld device has a manual system which operates by pressing a button to spray radioactive wash on the surface. The handheld device also has an electrical system which operates by pressing a button to suction radioactive contamination from the surface. The function of this system is to clean the surface from radioactive contamination. The system of the handheld device consists of a suctioning part and a pump and functions by suctioning the radioactive contamination into a lead cylinder, from which it is easily disposed. A third component includes a gauge for detecting contamination before, during, and after the cleaning and suctioning processes of the handheld device.

The method according to the present invention comprises using a high-frequency vibrating stirrer that is confirmed to include a treatment tank I, a high-frequency vibrating motor 3 fixed to a table positioned above the treatment tank 1, two vibrating rods 4 extending toward the bottom of the treatment tank 1 and coupled to the table, and multistage vibrating blades 5 mounted to the lower parts of the vibrating rods 4 and surface-plated with palladium or platinum serving as a catalyst in element transmutation, characterized in that the high frequency vibrating motor 3 is controlled by an inverter 6 so as to vibrate the multistage vibrating blades 5 at a frequency of 100-170 Hz in an aqueous solution 2 containing an element to be transmuted in the treatment tank 1, thereby transmuting the element in the aqueous solution 2 into another element. By adding heavy water to the solution to be treated, the transmutation efficiency can be elevated. By adding tritium water with an appropriate concentration as a substitute for the heavy water, the element transmutation can be completed within a short period of time and, at the same time, the tritium water that is seemingly the main cause of radioactive contamination can be effectively utilized and the radioactivity thereof can be attenuated or detoxified.

The method according to the present invention comprises using a high-frequency vibrating stirrer that is confirmed to include a treatment tank I, a high-frequency vibrating motor 3 fixed to a table positioned above the treatment tank 1, two vibrating rods 4 extending toward the bottom of the treatment tank 1 and coupled to the table, and multistage vibrating blades 5 mounted to the lower parts of the vibrating rods 4 and surface-plated with palladium or platinum serving as a catalyst in element transmutation, characterized in that the high frequency vibrating motor 3 is controlled by an inverter 6 so as to vibrate the multistage vibrating blades 5 at a frequency of 100-170 Hz in an aqueous solution 2 containing an element to be transmuted in the treatment tank 1, thereby transmuting the element in the aqueous solution 2 into another element. By adding heavy water to the solution to be treated, the transmutation efficiency can be elevated. By adding tritium water with an appropriate concentration as a substitute for the heavy water, the element transmutation can be completed within a short period of time and, at the same time, the tritium water that is seemingly the main cause of radioactive contamination can be effectively utilized and the radioactivity thereof can be attenuated or detoxified.

This invention has an object to provide a method for producing a beryllium solution, the method being novel and having high energy efficiency. The method (M10) for producing a beryllium solution includes a main heating step (S13) of dielectrically heating an acidic solution containing a starting material so as to generate a beryllium solution, the starting material being beryllium or a substance containing beryllium.

A radioactive sodium destruction facility includes a tank for storing liquid metallic sodium, located at a first level; a reaction vessel containing an aqueous solution; a sodium feed circuit comprising a sodium circulation member located at a second level higher than the first level, the circulation member having a suction in fluid communication with the tank and a discharge in fluid communication with the reaction vessel; an inert gas supply unit configured to supply the tank; a controller driving the sodium circulation member; and an inert gas supply unit configured to supply the tank; and a controller driving the supply unit to control a gas pressure in the tank, such that a pressure at the suction of the sodium circulation member is maintained within a predetermined range.

The invention relates to a technique for handling liquid radioactive waste from a nuclear fuel-energy cycle, and may be used in a process for processing liquid radioactive waste for maximally reducing the volume thereof and removing radionuclides by concentrating same in a solid phase. The aim is achieved by means of a method for processing liquid radioactive waste and for the recovery thereof, including waste oxidation, separating sludge, colloids and suspended particles from a liquid phase, and removing, from the liquid phase, radionuclides to be subsequently recovered using selective sorbents and filters; the method is characterized in that, prior to the stage for separating sludge, colloids and suspended particles from the liquid phase of the radioactive waste, selective sorbents in the form of powders are added and mixed into the liquid waste.

The invention relates to a technique for handling liquid radioactive waste from a nuclear fuel-energy cycle, and may be used in a process for processing liquid radioactive waste for maximally reducing the volume thereof and removing radionuclides by concentrating same in a solid phase. The aim is achieved by means of a method for processing liquid radioactive waste and for the recovery thereof, including waste oxidation, separating sludge, colloids and suspended particles from a liquid phase, and removing, from the liquid phase, radionuclides to be subsequently recovered using selective sorbents and filters; the method is characterized in that, prior to the stage for separating sludge, colloids and suspended particles from the liquid phase of the radioactive waste, selective sorbents in the form of powders are added and mixed into the liquid waste.

A method of activating and dewatering sludge through application of acoustic pressure shock waves to wastewater.

A method of activating and dewatering sludge through application of acoustic pressure shock waves to wastewater.

Provided is a method of treating radioactive liquid waste which reduces the amount of radioactive waste to be generated and is capable of removing a radioactive nuclide from radioactive liquid waste to the extent that the concentration thereof is less than or equal to the measurement lower limit using a simple apparatus configuration. A filtration device is connected to a colloid removal device by a connection pipe. An adsorption tower positioned at the highest stream of an adsorption device is connected to the colloid removal device by a connection pipe. The colloid removal device includes an electrostatic filter. Respective adsorption towers in the adsorption device are sequentially connected by a pipe. A discharge pipe is connected to the adsorption tower positioned at the lowest stream of the adsorption device. Radioactive liquid waste, containing particles having a particle diameter of 1 μm or greater, negatively charged colloids, and a radioactive nuclide, is supplied to the filtration device. The particles having a particle diameter of 1 μm or greater are removed by the filtration device and the negatively charged colloids are removed by the electrostatic filter that is positively charged. The radioactive nuclide is removed by the adsorption tower.