The present invention discloses a method for the separation of radionuclides from an aqueous radioactive waste solution, the method comprising: receiving of an aqueous radioactive waste solution, adding at least one zirconium salt to the aqueous radioactive waste solution, changing the pH of the radioactive waste solution to obtain a precipitate P, and separating the precipitate P from the radioactive waste solution. The present invention also discloses the use of zirconium salts, preferably zirconium oxychloride, zirconium nitrate or a zirconium oxynitrate or any mixture thereof, for the treatment of aqueous radioactive waste solution, preferably acidic or alkaline intermediate or low level radioactive waste solution, preferably an acidic intermediate and/or low level radioactive waste solution.

The present invention discloses a method for the separation of radionuclides from an aqueous radioactive waste solution, the method comprising: receiving of an aqueous radioactive waste solution, adding at least one zirconium salt to the aqueous radioactive waste solution, changing the pH of the radioactive waste solution to obtain a precipitate P, and separating the precipitate P from the radioactive waste solution. The present invention also discloses the use of zirconium salts, preferably zirconium oxychloride, zirconium nitrate or a zirconium oxynitrate or any mixture thereof, for the treatment of aqueous radioactive waste solution, preferably acidic or alkaline intermediate or low level radioactive waste solution, preferably an acidic intermediate and/or low level radioactive waste solution.

This invention is directed to amorphous and crystalline titanosilicate materials that have an unexpected selectivity for cesium and strontium, especially in the presence of high levels of competing ions. The titanosilicates of this invention show very high, unexpected selectivity in the presence of such competing cations such as sodium, calcium, magnesium and potassium, such as present in seawater.

This invention is directed to amorphous and crystalline titanosilicate materials that have an unexpected selectivity for cesium and strontium, especially in the presence of high levels of competing ions. The titanosilicates of this invention show very high, unexpected selectivity in the presence of such competing cations such as sodium, calcium, magnesium and potassium, such as present in seawater.

Resources, such as water, energy, power, amount of de-scaling chemicals, device lifetimes, data analytics and system depreciation may be conserved through the use of dual-field electric and magnetic probes that create and apply electromagnetic fields to liquids, such as water.

Resources, such as water, energy, power, amount of de-scaling chemicals, device lifetimes, data analytics and system depreciation may be conserved through the use of dual-field electric and magnetic probes that create and apply electromagnetic fields to liquids, such as water.

A dissolved air floatation apparatus including an ultrafine bubble-containing liquid production device and a dissolved air floatation tank. The ultrafine bubble-containing liquid production device includes a gas-liquid mixing unit and a bubble-containing liquid separation device. The bubble-containing liquid separation device swirls a liquid containing ultrafine bubbles and larger bubbles in a storage tank to concentrate the liquid that contains the ultrafine bubbles and the liquid that contains the larger bubbles to a central part of the swirling flow followed by discharge. A pressurized ultrafine bubble-containing liquid is mixed in a raw liquid containing a subject to be cleansed and is poured into the dissolved air floatation tank to cause a suspended substance and a dissolved component in the raw liquid to be adsorbed on an interface of fine bubbles and be floated in the dissolved air floatation tank to be extracted.

A dissolved air floatation apparatus including an ultrafine bubble-containing liquid production device and a dissolved air floatation tank. The ultrafine bubble-containing liquid production device includes a gas-liquid mixing unit and a bubble-containing liquid separation device. The bubble-containing liquid separation device swirls a liquid containing ultrafine bubbles and larger bubbles in a storage tank to concentrate the liquid that contains the ultrafine bubbles and the liquid that contains the larger bubbles to a central part of the swirling flow followed by discharge. A pressurized ultrafine bubble-containing liquid is mixed in a raw liquid containing a subject to be cleansed and is poured into the dissolved air floatation tank to cause a suspended substance and a dissolved component in the raw liquid to be adsorbed on an interface of fine bubbles and be floated in the dissolved air floatation tank to be extracted.

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.