The present invention relates to a method of separating radioactive elements from a mixture, wherein the mixture is treated with at least one alkanesulfonic acid and at least one further acid, selected from the group consisting of hydrochloric acid, nitric acid, amidosulfonic acid and mixtures thereof and also the use of at least one alkanesulfonic acid and at least one further acid for separating radioactive elements from mixtures comprising these.

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.

A furnace isolation chamber for containing a component to be Hot Isostatically Pressed is disclosed. The disclosed furnace includes inherent passive features to assist in the containment of released toxic gases via a thermal gradient within the chamber. The chamber comprises longitudinally cylindrical sidewalls; a top end extending between and permanently connected to the sidewalls, thereby closing one end of the chamber; and a movable bottom end, which is opposite the top end and forms a base end of the chamber. The movable bottom end is adapted to receive the component, and comprises a mechanism for raising and lowering the component into the high temperature zone of the furnace in the HIP system. The isolation chamber forms an integral part of the HIP system with the base end of the chamber comprising a cool zone as a result of being located outside of the high temperature zone of the furnace.

This geopolymer molding production method comprises: a mixing step (S1) for mixing a first material containing aluminum and silicon with a hydrate of an alkali stimulant containing a hydrate of an alkaline hydroxide and/or a hydrate of an alkaline silicate; a compaction step (S2) for compacting the mixture obtained in the mixing step (S1) into a compacted mixture; and a curing step (S3) for curing the compacted mixture.

The present invention relates to methods of decontaminating irradiated nuclear graphite. The method comprises immersing the irradiated nuclear graphite in a molten salt electrolyte, and subjecting the irradiated nuclear graphite to an electrochemical treatment.

A method for treatment of spent ion-exchange resins for disposal includes feeding a mixture of spent ion-exchange resins to the a loading tank, separating the ion-exchange resins, feeding separated ion-exchange resins into the a drying chamber, vacuum drying the ion-exchange resins and subjecting the resins to additional heat treatment in a high-temperature furnace, and unloading the treated ion-exchange resins into a transport container. A device for treatment of spent ion-exchange resins includes a loading tank, a metering device connected to a drying chamber, an inclined feed screw located between the loading tank and the metering device, a vacuum pump, a heated gas filter, a high-temperature furnace equipped with a vacuum drying and gas purification system, and a feeding device located between the drying chamber and the high-temperature furnace. A docking unit is connected to a lower part of the high-temperature furnace.

A method and apparatus for the electrochemical removal of material from a surface in which two or more fluid jets or flows are arranged to impinge on the surface of the object and an electrical current flows through one fluid flow path, through the object, and then through a second fluid flow path.

Devices for eliminating radioactive contamination of radioactive waste by providing adaptive processing of the decontamination solution for reuse. The plant for electrochemical decontamination of metal radioactive waste includes a pipe equipped with shut-off valves, a radioactive waste processing module that comprises a unit for electrochemical decontamination connected by a ventilation channel to the ventilation module and pipe for decontamination solution supply and discharge equipped with shut-off valves. The plant is equipped with a decontamination solution preparation module connected with a pipe for decontamination solution supply and discharge, at least one pump, while the module for decontamination solution receiving is equipped with devices for cleaning and pH correction of decontamination solution, and the unit for electrochemical decontamination of metal radioactive waste, the module for decontamination solution receiving and the decontamination solution preparation module are equipped with pH measurement elements.

A method for decommissioning a nuclear facility includes: separating a nuclear reactor pressure vessel from biodegradable concrete; decommissioning a concrete structure; covering the biodegradable concrete; and decommissioning the biodegradable concrete.

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.