The invention relates to the reprocessing of spent ion-exchange resins at nuclear power plants or special plants. The invention involves microencapsulation of ion-exchange resins (immobilization of radionuclides inside microcapsules), reducing the volume of discharged ion-exchange resins and preventing their swelling when exposed to moisture. A method for treatment of spent ion-exchange resins for disposal comprises feeding a mixture of spent ion-exchange resins to the loading tank, separating the ion-exchange resins, feeding separated ion-exchange resins into the drying chamber, vacuum drying of the ion-exchange resins, unloading the treated ion-exchange resin into a transport container. The ion-exchange resins after vacuum drying are subjected to additional heat treatment in a high-temperature furnace and unloading treated ion-exchange resin in a transport container. The invention reduces the volume of unloaded ion-exchange resins by more than 2 times, ensuring their swelling no more than 10%, and preventing the immobilization of radionuclides inside microcapsules.

A device comprises a raw material conveyor, a raw material mixer, a liquid waste conveying pipeline, an additive tank, a powder waste conveyor, an output pump, a liquid supply pump, a liquid supply manifold, an output manifold, a mixed liquid conveying pipeline, a high-pressure injection pump, a high-pressure pipeline, and a wellhead sealing device. The method includes: drilling a well; forming a fracture in the granite stratum; preparing a raw material; and injecting, by using a disposal device, a sand-carrying feed liquid from a high-pressure injection pump into the fracture of the underground granite stratum, so as to perform solidification. The method has low cost, high disposal efficiency, simple device structure, high usability, safety and reliability, and an effective reduction in nuclear waste contamination and hazards to the environment.

A device comprises a raw material conveyor, a raw material mixer, a liquid waste conveying pipeline, an additive tank, a powder waste conveyor, an output pump, a liquid supply pump, a liquid supply manifold, an output manifold, a mixed liquid conveying pipeline, a high-pressure injection pump, a high-pressure pipeline, and a wellhead sealing device. The method includes: drilling a well; forming a fracture in the granite stratum; preparing a raw material; and injecting, by using a disposal device, a sand-carrying feed liquid from a high-pressure injection pump into the fracture of the underground granite stratum, so as to perform solidification. The method has low cost, high disposal efficiency, simple device structure, high usability, safety and reliability, and an effective reduction in nuclear waste contamination and hazards to the environment.

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.

The invention relates to means for protecting the environment from the consequences of fires complicated by a radiation factor. A composition for dust suppression and containment of radioactive products of combustion after a fire with a radiation factor has been extinguished comprises, as a surfactant, a mixture of an anionic, a non-ionic and an amphoteric surfactant, and has the following ratio of components: 3.0-7.0% by weight of an aqueous solution of polyvinyl alcohol (in terms of a mass fraction of dry product); 0.1-0.3% by weight of plasticizer; 11.0-29.0% by weight of surfactant; with water making up the remainder. The invention makes it possible to carry out dust suppression and containment of radioactive products of combustion which are formed on surfaces, including at elevated temperatures, after a fire has been extinguished.

The present invention is about a process for the treatment of radioactive liquid sewage, deriving from nuclear plants or hospital waste containing various metals, non-metals and organic compounds, in order to transform this sewage into a vitreous body safely retaining the nuclear elements or isotopes in a silica matrix; the invention also regards an apparatus for implementing the process in an automated way.

The present invention is about a process for the treatment of radioactive liquid sewage, deriving from nuclear plants or hospital waste containing various metals, non-metals and organic compounds, in order to transform this sewage into a vitreous body safely retaining the nuclear elements or isotopes in a silica matrix; the invention also regards an apparatus for implementing the process in an automated way.

A waste extraction system includes a precipitation tank comprising a waste stream input, a solution input, and a waste stream output, wherein the waste stream input is fluidly coupled to an upstream segment of a main waste pathway, a column effluent tank, an adsorption column positioned between and fluidly coupled to the precipitation tank and the column effluent tank along the main waste pathway, wherein the adsorption column houses an ion exchange resin and is positioned downstream the precipitation tank, a solution pathway extending from a solution source to the solution input of the precipitation tank, the solution source housing an alkaline solution, and a particle filtration unit positioned between and fluidly coupled to the precipitation tank and the adsorption column.

The present invention relates to a method for removing cesium in a clay mineral using hydrogen peroxide. According to the present invention, cesium in a clay mineral is removed using hydrogen peroxide, which serves to induce interlayer expansion of the clay mineral to allow a cation to easily enter an interlayer of the clay mineral, and thus cesium desorption efficiency can be further improved. Also, the method according to the present invention can be efficiently used to restore soil in residential areas widely contaminated with a radionuclide when a major accident such as Fukushima nuclear accident occurs as well as various sites of atomic energy facilities contaminated with a radionuclide. Also, since radiation-contaminated soil is treated with only hydrogen peroxide and cations, secondary environmental pollution caused by wastes can be significantly reduce and the waste disposing cost can also be saved.

Systems and/or methods of waste disposal use human-made caverns that are constructed within deep geological formations. A given human-made cavern may be constructed by first drilling out a vertical wellbore to a deep geological formation. Then a bottom portion of the vertical wellbore is jet drilled using an abrasive jetting fluid to form a launch chamber of void volume, that is sized to fit a reaming tool in its deployed open configuration. A reaming tool, in a closed configuration, is then inserted into the vertical wellbore for landing in the launch chamber. The reaming tool is then deployed into its open configuration while in the launch chamber. Reaming operations then occur from the launch chamber directed downwards within the deep geological formation, forming a given human-made cavern. The newly formed human-made cavern may be conditioned and/or configured for receiving amounts of the waste for long-term disposal and/or storage.