The invention relates to technology for processing liquid radioactive waste containing, inter alia, tritium isotopes, which are formed in various nuclear industry plants, and also during decommissioning of such plants. The technical result of the claimed invention consists in simplifying the technological procedure for processing liquid radioactive waste containing, inter alia, tritium isotopes by excluding complicated and lengthy operations associated with testing a concrete mixture produced from deactivated liquid radioactive waste, and also in increasing the ecological safety by reducing the size of areas for storage of the waste produced during the processing of the liquid radioactive waste. The claimed technical result is achieved in that a method for processing liquid radioactive waste containing, inter alia, tritium isotopes involves removing radioactive substances from the liquid radioactive waste so as to produce a low-level waste solution, and introducing a binder into the low-level waste solution produced in order to prepare a concrete mixture which complies with structural, radioecological, and sanitary and hygiene requirements, wherein components that have a negative effect on the technical characteristics of the concrete mixture being produced are removed from the low-level waste solution before the binder is added.

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 relates to a chitosan-titanium composite, a preparation method and use thereof, and more particularly, a chitosan-titanium composite capable of effectively adsorbing and desorbing .sup.68Ge/.sup.68Ga by combining small molecular chitosan with titanium metal oxide to increase adsorption reactivity to .sup.68Ge and .sup.68Ga desorption reactivity, and a preparation method and use thereof.

Methods of disposing of liquid radioactive medical waste are disclosed. The methods relate to depositing liquid radioactive medical waste into or onto a substrate that includes (a)(i) fibers, or (ii) both fibers and foam, and (b) activated carbon. The substrate adsorbs liquid radioactive medical waste to facilitate safe disposal of liquid radioactive medical waste.

Waste disposal substrates are also disclosed. The waste disposal substrates include (a) at least one layer of fibers, (b) at least one layer containing activated carbon; and (c) at least one layer containing superabsorbent particles. Methods of using waste disposal substrates are also disclosed. Methods of using a waste disposal substrate may include contacting a waste disposal substrate with a liquid fluid, the waste disposal substrate containing: (a) at least one layer of fibers, (b) at least one layer containing activated carbon; and (c) at least one layer containing superabsorbent particles. The liquid fluid, or a component of the liquid fluid, is collected, dissolved, adsorbed, inactivated, destroyed, and/or disposed of within the waste disposal substrate.

Methods of disposing of liquid radioactive medical waste are disclosed. The methods relate to depositing liquid radioactive medical waste into or onto a substrate that includes (a)(i) fibers, or (ii) both fibers and foam, and (b) activated carbon. The substrate adsorbs liquid radioactive medical waste to facilitate safe disposal of liquid radioactive medical waste.

Waste disposal substrates are also disclosed. The waste disposal substrates include (a) at least one layer of fibers, (b) at least one layer containing activated carbon; and (c) at least one layer containing superabsorbent particles. Methods of using waste disposal substrates are also disclosed. Methods of using a waste disposal substrate may include contacting a waste disposal substrate with a liquid fluid, the waste disposal substrate containing: (a) at least one layer of fibers, (b) at least one layer containing activated carbon; and (c) at least one layer containing superabsorbent particles. The liquid fluid, or a component of the liquid fluid, is collected, dissolved, adsorbed, inactivated, destroyed, and/or disposed of within the waste disposal substrate.

A silver-doped, nano-porous hydroxyapatite material is provided that can be utilized to capture radioactive iodine, .sup.129I. Methods of using the silver-doped, nano-porous hydroxyapatite material to remove radioactive iodine, and methods of manufacturing the material are also provided.

A silver-doped, nano-porous hydroxyapatite material is provided that can be utilized to capture radioactive iodine, .sup.129I. Methods of using the silver-doped, nano-porous hydroxyapatite material to remove radioactive iodine, and methods of manufacturing the material are also provided.

An ion exchange system includes an ion exchange column filled with ion exchange media and a passive cooling system. The passive cooling system includes a working fluid that transfers heat away from the ion exchange column. In one embodiment, the working fluid is in a closed system. In another embodiment, the passive cooling system includes a heat pipe. In yet another embodiment, the ion exchange system is used to separate radionuclides, such as Cs-137 from a liquid waste stream.

An ion exchange system includes an ion exchange column filled with ion exchange media and a passive cooling system. The passive cooling system includes a working fluid that transfers heat away from the ion exchange column. In one embodiment, the working fluid is in a closed system. In another embodiment, the passive cooling system includes a heat pipe. In yet another embodiment, the ion exchange system is used to separate radionuclides, such as Cs-137 from a liquid waste stream.

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.