An electrolytic enrichment method for heavy water includes enriching heavy water by electrolysis using an alkaline water electrolysis cell including an anode chamber that holds an anode, a cathode chamber that holds a cathode, and a diaphragm. In the method, an electrolyte prepared by adding high-concentration alkaline water to raw material water containing heavy water is circularly supplied to the anode chamber and the cathode chamber from a circulation tank; an anode-side gas-liquid separator and an anode-side water-seal device are connected to the anode chamber, and a cathode-side gas-liquid separator and a cathode-side water-seal device are connected to the cathode chamber; and electrolysis is continued while the alkali concentration in the electrolyte supplied to both electrolysis chambers is maintained at a constant concentration by circularly supplying, to the circulation tank, the electrolyte from which the gas generated from the anode-side gas-liquid separator and the cathode-side gas-liquid separator is separated.

The present invention relates to a method for treating tritium water-containing raw water, the method including supplying a part of raw water containing tritium water and alkali water to a circulation tank, mixing the raw water with alkali water in the circulation tank to obtain an electrolyte adjusted so as to have a desired alkali concentration, and continuously electrolyzing the electrolyte while circulating the electrolyte, thereby subjecting the raw water stored in the storage tank to alkali water electrolysis and thus gasifying the raw water. According to the invention, by gasifying tritium water-containing raw water by alkali water electrolysis, the tritium concentration in a tritium-containing hydrogen gas is diluted to 1/1,244 and the tritium water-containing raw water can be reduced in volume.

The present invention relates to a method for treating tritium water-containing raw water, the method including supplying a part of raw water containing tritium water and alkali water to a circulation tank, mixing the raw water with alkali water in the circulation tank to obtain an electrolyte adjusted so as to have a desired alkali concentration, and continuously electrolyzing the electrolyte while circulating the electrolyte, thereby subjecting the raw water stored in the storage tank to alkali water electrolysis and thus gasifying the raw water. According to the invention, by gasifying tritium water-containing raw water by alkali water electrolysis, the tritium concentration in a tritium-containing hydrogen gas is diluted to 1/1,244 and the tritium water-containing raw water can be reduced in volume.

The present invention relates to a method for treating tritium water-containing raw water, the method including supplying a part of raw water containing tritium water and alkali water to a circulation tank, mixing the raw water with alkali water in the circulation tank to obtain an electrolyte adjusted so as to have a desired alkali concentration, and continuously electrolyzing the electrolyte while circulating the electrolyte, thereby subjecting the raw water stored in the storage tank to alkali water electrolysis and thus gasifying the raw water.

According to the invention, by gasifying tritium water-containing raw water by alkali water electrolysis, the tritium concentration in a tritium-containing hydrogen gas is diluted to 1/1,244 and the tritium water-containing raw water can be reduced in volume.

The present invention relates to a method for treating tritium water-containing raw water, the method including supplying a part of raw water containing tritium water and alkali water to a circulation tank, mixing the raw water with alkali water in the circulation tank to obtain an electrolyte adjusted so as to have a desired alkali concentration, and continuously electrolyzing the electrolyte while circulating the electrolyte, thereby subjecting the raw water stored in the storage tank to alkali water electrolysis and thus gasifying the raw water.

According to the invention, by gasifying tritium water-containing raw water by alkali water electrolysis, the tritium concentration in a tritium-containing hydrogen gas is diluted to 1/1,244 and the tritium water-containing raw water can be reduced in volume.

A method and an apparatus for the treatment of waste ion exchange resins containing radionuclides, and the present invention relates to a method for the treatment of waste ion exchange resins containing radionuclides by the stepwise heat treatment and an apparatus to accomplish the said method.

A method and an apparatus for the treatment of waste ion exchange resins containing radionuclides, and the present invention relates to a method for the treatment of waste ion exchange resins containing radionuclides by the stepwise heat treatment and an apparatus to accomplish the said method.

The present disclosure relates to nuclear chemical, particularly radiochemical, technologies at different stages of the nuclear fuel cycle, such as the production of purified nuclear materials (uranium, zirconium) or the reprocessing of spent nuclear fuel from nuclear power stations, in which extraction processes and operations for purifying nuclear materials are used. An example method, which includes the partial decomposition of nitric acid during continuous evaporation while a solution containing a reducing agent is fed into the bottom part of an evaporator having a circulating bottoms solution, consists in that the process is carried out such that the solution is kept in the bottom part of the evaporator for more than 2 hours under the addition of an aqueous solution of formaldehyde and formic acid (hereinafter the mixture) or a solution of formic acid after the process has been started using the mixture.

The present disclosure relates to nuclear chemical, particularly radiochemical, technologies at different stages of the nuclear fuel cycle, such as the production of purified nuclear materials (uranium, zirconium) or the reprocessing of spent nuclear fuel from nuclear power stations, in which extraction processes and operations for purifying nuclear materials are used. An example method, which includes the partial decomposition of nitric acid during continuous evaporation while a solution containing a reducing agent is fed into the bottom part of an evaporator having a circulating bottoms solution, consists in that the process is carried out such that the solution is kept in the bottom part of the evaporator for more than 2 hours under the addition of an aqueous solution of formaldehyde and formic acid (hereinafter the mixture) or a solution of formic acid after the process has been started using the mixture.

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.