An activating agent for the treatment of radioactive wastewater. The activating agent is prepared by dissolving a mixture of inorganic salts including Ca.sup.2+, Na.sup.+, Sr.sup.2+, Zn.sup.2+, Mg.sup.2+, Fe.sup.2+ and K.sup.+ in pure water having an electrical resistivity greater than 0.5 M.Math.cm to yield a solution. A method of radioactive wastewater treatment using the activating agent includes: 1) preparing the activating agent; 2) adding the activating agent to radioactive wastewater having an electrical resistivity greater than 0.5 M.Math.cm; uniformly mixing the activating agent and the radioactive wastewater; 3) further treating the radioactive wastewater including the activating agent using an electro-deionization device; and 4) collecting two liquid flows obtained in 3), one being purified water, the other being concentrated water returning to 2) for further purification.

An activating agent for the treatment of radioactive wastewater. The activating agent is prepared by dissolving a mixture of inorganic salts including Ca.sup.2+, Na.sup.+, Sr.sup.2+, Zn.sup.2+, Mg.sup.2+, Fe.sup.2+ and K.sup.+ in pure water having an electrical resistivity greater than 0.5 M.Math.cm to yield a solution. A method of radioactive wastewater treatment using the activating agent includes: 1) preparing the activating agent; 2) adding the activating agent to radioactive wastewater having an electrical resistivity greater than 0.5 M.Math.cm; uniformly mixing the activating agent and the radioactive wastewater; 3) further treating the radioactive wastewater including the activating agent using an electro-deionization device; and 4) collecting two liquid flows obtained in 3), one being purified water, the other being concentrated water returning to 2) for further purification.

Methods and devices for directing a waste fluid from a radiopharmaceutical synthesis system to a waste vessel are provided. In one example, the method includes serially connecting a primary waste vessel to a secondary waste vessel with a fluid conduit, including a waste valve connected to the fluid conduit extending between the primary waste vessel and secondary waste vessel; opening the waste valve so as to allow fluid communication between cavities of the primary and secondary waste vessels; drawing a low pressure in both waste vessels; closing the waste valve so as to fluidically isolate the secondary waste vessel from the primary waste vessel, discharging the waste fluid through a pump valve into the primary waste vessel, and opening the waste valve to evacuate the waste fluid from the primary waste vessel into the secondary waste vessel.

Methods and devices for directing a waste fluid from a radiopharmaceutical synthesis system to a waste vessel are provided. In one example, the method includes serially connecting a primary waste vessel to a secondary waste vessel with a fluid conduit, including a waste valve connected to the fluid conduit extending between the primary waste vessel and secondary waste vessel; opening the waste valve so as to allow fluid communication between cavities of the primary and secondary waste vessels; drawing a low pressure in both waste vessels; closing the waste valve so as to fluidically isolate the secondary waste vessel from the primary waste vessel, discharging the waste fluid through a pump valve into the primary waste vessel, and opening the waste valve to evacuate the waste fluid from the primary waste vessel into the secondary waste vessel.

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.

Apparatuses for treating radioactive material using a multi-membrane are disclosed. The apparatus for treating radioactive material uses a multi-membrane capable of increasing the usage capacity and life of the storage tank with a multi-membrane process by discharging liquid (e.g., water in waste water) in which radioactive material is removed from waste water to the outside and by storing solidified waste containing radioactive material in the storage tank.

Apparatuses for treating radioactive material using a multi-membrane are disclosed. The apparatus for treating radioactive material uses a multi-membrane capable of increasing the usage capacity and life of the storage tank with a multi-membrane process by discharging liquid (e.g., water in waste water) in which radioactive material is removed from waste water to the outside and by storing solidified waste containing radioactive material in the storage tank.

An activating agent for the treatment of radioactive wastewater. The activating agent is prepared by dissolving a mixture of inorganic salts including Ca.sup.2+, Na.sup.+, Sr.sup.2+, Zn.sup.2+, Mg.sup.2+, Fe.sup.2+ and K.sup.+ in pure water having an electrical resistivity greater than 0.5 M.Math.cm to yield a solution. A method of radioactive wastewater treatment using the activating agent includes: 1) preparing the activating agent; 2) adding the activating agent to radioactive wastewater having an electrical resistivity greater than 0.5 M.Math.cm; uniformly mixing the activating agent and the radioactive wastewater; 3) further treating the radioactive wastewater including the activating agent using an electro-deionization device; and 4) collecting two liquid flows obtained in 3), one being purified water, the other being concentrated water returning to 2) for further purification.