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.

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.

The present invention provides systems, apparatuses, and methods for the treatment of containerized waste, such as hazardous, radioactive and/or mixed waste. The apparatuses and methods employ a combination of thermal decomposition and specialized lances.

Recycling of low and medium radioactivity nuclear waste from VVER and RBMK reactors and other nuclear installations.

The invention uses a recycling plant consisting of a waste feed unit; a plasma shaft-type furnace with a melter in the hearth of the furnace and a slug discharge unit connected with a receiving tank for molten slug; an air supply unit delivering air to the furnace to a pyrolysis gas combustion chamber; an evaporative heat exchanger for sharp reduction of the flue gases temperature; a gas purification unit with a sock-type filter; a heat-exchanger and a scrubber; pumps and tanks for agents and recycled products; fittings; and at least, one control module which is electrically connected to the slug discharge control module, an interior environment control module, an equipment status control module and, at least, one gas analytical module.

Disclosed is a liquid-phase oxidative decomposition method for radioactively contaminated carbonaceous material, providing a method of oxidizing carbon into a gas in liquid phase to treat radioactively contaminated carbonaceous material. The method comprises the following steps: ball milling a mixture of a molybdenum-containing substance and a carbonaceous material, thermally treating the ball milled mixture, and performing liquid-phase oxidation of the thermally treated mixture. The thermal treatment causes carbon to enter space between molybdenum atoms so as to reduce the particle size of carbon and improve the chemical reactivity of carbon, and an oxidant is then used to oxidize the carbon in the space between molybdenum atoms into a gas in liquid phase, while the molybdenum-containing moiety is converted into a water-soluble substance. The method of has technical effects of mild reaction conditions, low energy consumption, high operation safety, and facilitates the recovery of elements attached to carbonaceous material.

Disclosed is a liquid-phase oxidative decomposition method for radioactively contaminated carbonaceous material, providing a method of oxidizing carbon into a gas in liquid phase to treat radioactively contaminated carbonaceous material. The method comprises the following steps: ball milling a mixture of a molybdenum-containing substance and a carbonaceous material, thermally treating the ball milled mixture, and performing liquid-phase oxidation of the thermally treated mixture. The thermal treatment causes carbon to enter space between molybdenum atoms so as to reduce the particle size of carbon and improve the chemical reactivity of carbon, and an oxidant is then used to oxidize the carbon in the space between molybdenum atoms into a gas in liquid phase, while the molybdenum-containing moiety is converted into a water-soluble substance. The method of has technical effects of mild reaction conditions, low energy consumption, high operation safety, and facilitates the recovery of elements attached to carbonaceous material.

The present invention relates to a method for separating cesium and technetium from radioactive waste, which method comprises the sublimation of cesium pertechnetate, and an apparatus for carrying out this method. The separation includes the steps of obtaining the two elements cesium and technetium together from the waste and subsequently separating the two elements from each other. The aim of the present invention is to significantly reduce the activity of radioactive solid waste and to use the obtained radionuclides in an economical and technical manner. Additionally, the method allows elements of cesium and technetium to be separated directly from the operation of a vitrification, sintering, drying, combustion, cementing, or calcinating plant, thus obviating additional problems when carrying out the process.

The present invention relates to a sealed plasma melting furnace for treating low- and intermediate-level radioactive waste, which allows the secondary pollutants to be minimized. The sealed plasma melting furnace includes: a waste supply chamber communicatively provided with a hopper; a pyrolysis chamber channel communicatively coupled with the waste supply chamber; a pyrolysis chamber having a burner mounted thereon; a melting chamber channel guiding the waste transferred from the pyrolysis chamber communicatively provided therewith to fall down; a melting chamber provided with a furnace interior portion accommodating a molten substance on a bottom surface thereof; a processed molten substance discharge channel discharging the processed molten substance generated in the melting chamber; a secondary combustion chamber channel inducing and exhausting an off-gas flow generated in the melting chamber; and a secondary combustion chamber inducing complete combustion of the off-gas input from the secondary combustion chamber channel.

The present invention relates to a sealed plasma melting furnace for treating low- and intermediate-level radioactive waste, which allows the secondary pollutants to be minimized. The sealed plasma melting furnace includes: a waste supply chamber communicatively provided with a hopper; a pyrolysis chamber channel communicatively coupled with the waste supply chamber; a pyrolysis chamber having a burner mounted thereon; a melting chamber channel guiding the waste transferred from the pyrolysis chamber communicatively provided therewith to fall down; a melting chamber provided with a furnace interior portion accommodating a molten substance on a bottom surface thereof; a processed molten substance discharge channel discharging the processed molten substance generated in the melting chamber; a secondary combustion chamber channel inducing and exhausting an off-gas flow generated in the melting chamber; and a secondary combustion chamber inducing complete combustion of the off-gas input from the secondary combustion chamber channel.

Treatment of radioactive waste comprising organic compounds and sulfur-containing compounds and/or halogen-containing compounds. An apparatus comprises a reaction vessel comprising a filter for carrying out thermal treatment of the waste and a thermal oxidizer. Utilizing co-reactants to reduce gas phase sulfur and halogen from treatment of wastes.