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.

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.

There is disclosed a nuclearized hot-isostatic press (HIP) system comprising, a high temperature HIP furnace and a multi-wall vessel surrounding the furnace, such as a dual walled vessel comprising concentric vessels. The described multi-walled vessel comprises at least one detector contained between the walls to detect a gas leak, a crack in a vessel wall, or both. The disclosed HIP system also comprises multiple heads located on top and underneath the furnace, a yoke frame, and a lift for loading and unloading a HIP can to the high temperature HIP furnace. There is also disclosed a method of using such a system to provide ease of maintenance, operation, decontamination and decommissioning.

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.

Provided is an induction heating device with which discharging can be easily avoided even when a large electric current is used. The induction heating device comprises a high-frequency power supply provided with a connection portion for an alternating-current power supply, and a heating coil portion connected to the high-frequency power supply. In the heating coil portion, a plurality of coils include n coils surrounding a cavity portion in a plane, wherein the plurality of coils are mutually connected in series via one of a plurality of capacitors.

A method of disposing of uranium oxides and of disposing of metal casks that had formerly held uranium hexafluoride may include steps of: (a) receiving at least a quantity of at least one type of uranium oxide; (b) receiving at least one metal cask selected from the metal casks that was formerly housing at least some quantity of the uranium hexafluoride; (c) cutting up and/or shredding the at least one metal cask into smaller pieces; and (d) loading at least some of the quantity of the at least one type of uranium oxide and/or loading at least some of the smaller pieces into one or more human-made caverns. The one or more human-made caverns may be located within at least one deeply located geologic (rock) formation. The at least one deeply located geologic (rock) formation may be located at least 2,000 feet vertically below a terrestrial surface of the Earth.

A method of disposing of uranium oxides and of disposing of metal casks that had formerly held uranium hexafluoride may include steps of: (a) receiving at least a quantity of at least one type of uranium oxide; (b) receiving at least one metal cask selected from the metal casks that was formerly housing at least some quantity of the uranium hexafluoride; (c) cutting up and/or shredding the at least one metal cask into smaller pieces; and (d) loading at least some of the quantity of the at least one type of uranium oxide and/or loading at least some of the smaller pieces into one or more human-made caverns. The one or more human-made caverns may be located within at least one deeply located geologic (rock) formation. The at least one deeply located geologic (rock) formation may be located at least 2,000 feet vertically below a terrestrial surface of the Earth.

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.

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.

The present invention relates to a mobile compacting and melting complex volume reduction system (1) of radioactive waste. The complex volume reduction system (1) includes a mobile vehicle (3); a volume reducing part (7) that is disposed at one side of the inside of a container (5) mounted on the vehicle (3), and that presses and compacts dry active waste; a melting part (9) that is disposed at one side of the inside of the container (5) to melt the dry active waste by heat of a high temperature; and an exhaust gas processing part (11) that is connected to the melting part (9) to exhaust discharged gas to the outside.