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.

Apparatus for drying Spent Ion-Exchange Resins (SIER), which can intensify the SIER drying process, reduce power consumption, and accelerate discharge of SIER when the drying process is completed. The apparatus comprises a sealed cylindrical body, and a blow-down choke installed in an upper part of the sealed cylindrical body and a nozzle to feed the spent ion-exchange resins is installed inside the body, and a nozzle to retrieve dried ion-exchange resins is installed in its bottom part and equipped with a locking device. An external heater is provided for the body, and a drive shaft that is installed in alignment inside the body, capable of rotation, and equipped with a stirrer. A lower part of the drive shaft with lower screw winding is installed in alignment inside the nozzle to retrieve dried ion-exchange resins. The nozzle to retrieve dried ion-exchange resins is equipped with a water draining device.

Apparatus for drying Spent Ion-Exchange Resins (SIER), which can intensify the SIER drying process, reduce power consumption, and accelerate discharge of SIER when the drying process is completed. The apparatus comprises a sealed cylindrical body, and a blow-down choke installed in an upper part of the sealed cylindrical body and a nozzle to feed the spent ion-exchange resins is installed inside the body, and a nozzle to retrieve dried ion-exchange resins is installed in its bottom part and equipped with a locking device. An external heater is provided for the body, and a drive shaft that is installed in alignment inside the body, capable of rotation, and equipped with a stirrer. A lower part of the drive shaft with lower screw winding is installed in alignment inside the nozzle to retrieve dried ion-exchange resins. The nozzle to retrieve dried ion-exchange resins is equipped with a water draining device.

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.

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.

A method for reducing radiologically-contaminated waste is provided. The method comprises treating radiologically-contaminated surfaces and subsurfaces. The method comprises consolidating soil waste. The method comprises employing real-time scanning technology to classify waste based at least in part on a threshold of radiological contamination. The waste is sorted based on the classification. The waste is disposed of via at least one of different disposal routes, based at least in part on the classification.

The invention relates to an encapsulation composition for the storage or the confinement of waste which is toxic to health and/or the environment, comprising a resin composition containing at least one epoxy resin, and a hardening composition containing at least one polyamidoamine and at least one aromatic polyamine, said encapsulation composition having an aromaticity rate which is equal to, or higher than, 35%. The invention also relates to the use of said composition for encapsulating said waste.

This invention relates to a solidifying agent for solidifying radioactive waste, and more particularly to a solidifying-agent composition for solidifying radioactive waste, including alumina cement and a gypsum powder. The solidifying-agent composition including alumina cement and a gypsum powder is capable of effectively minimizing an increase in the volume of a solidified radioactive waste product to a level satisfying physical and chemical safety regulations upon the solidification of radioactive waste.

This invention relates to a solidifying agent for solidifying radioactive waste, and more particularly to a solidifying-agent composition for solidifying radioactive waste, including alumina cement and a gypsum powder. The solidifying-agent composition including alumina cement and a gypsum powder is capable of effectively minimizing an increase in the volume of a solidified radioactive waste product to a level satisfying physical and chemical safety regulations upon the solidification of radioactive waste.