A dismantling and decontamination system of biodegradable concrete of a nuclear power plant according to an exemplary embodiment includes: a dismantling device for dismantling an in-core instrument installed under biodegradable concrete to form a lower penetrated part of the biodegradable concrete; a decontamination device inserted inside the biodegradable concrete for decontaminating radioactive waste of the inner wall of the biodegradable concrete; a waste receiving device movable through the lower penetrated part of the biodegradable concrete; and a blocking device for blocking the upper opening of the biodegradable concrete to block an outflow of the radioactive dust.

Decontamination method for a nuclear reactor design component, comprising treating the nuclear reactor design component with a low-temperature plasma under the flow of reactionless gas. A selected site on the surface of the design component is supplied to the electrode. Plasma discharge is ignited between the surface of the design component chosen as the cathode, and the electrode chosen as the anode. Operating parameters of the discharge effective to sputtering of the cathode are chosen. The cathode is sputtered. The electrode and a gas pipeline diverting inert gas from the discharge zone are cooled to a temperature sufficient for the precipitation of the sputtered atoms on the surface of the electrode and lines. After sputtering the cathode to the specified depth, the electrode is moved to a new area of treatment and the process steps are repeated until the complete treatment of the entire surface of the design component.

The present invention provides systems, methods and devices for storing and/or disposing of hazardous waste material. In some embodiments, the waste material includes nuclear waste such as calcined material. In certain embodiments, the device includes a container having a container body, a filling port configured to couple with a filling nozzle and a filling plug, and an evacuation port having a filter. The evacuation port is configured to couple with an evacuation nozzle and an evacuation plug. In certain embodiments, the method includes (a) adding hazardous waste material via a filling nozzle coupled to a filling port of a container, the container including an evacuation port, (b) evacuating the container during adding of the hazardous waste material via an evacuation nozzle coupled to an evacuation port of the container, (c) sealing the filling port, (d) heating the container, and (e) sealing the evacuation port.

Devices for eliminating radioactive contamination of radioactive waste by providing adaptive processing of the decontamination solution for reuse. The plant for electrochemical decontamination of metal radioactive waste includes a pipe equipped with shut-off valves, a radioactive waste processing module that comprises a unit for electrochemical decontamination connected by a ventilation channel to the ventilation module and pipe for decontamination solution supply and discharge equipped with shut-off valves. The plant is equipped with a decontamination solution preparation module connected with a pipe for decontamination solution supply and discharge, at least one pump, while the module for decontamination solution receiving is equipped with devices for cleaning and pH correction of decontamination solution, and the unit for electrochemical decontamination of metal radioactive waste, the module for decontamination solution receiving and the decontamination solution preparation module are equipped with pH measurement elements.

A method for decommissioning a nuclear facility includes: separating a nuclear reactor pressure vessel from biodegradable concrete; decommissioning a concrete structure; covering the biodegradable concrete; and decommissioning the biodegradable concrete.

A radioactive structure dismantling method of a heavy water reactor facility that includes a calandria including a main shell and a sub shell, a calandria vault that receives the calandria therein, and a cover assembly that covers the calandria according to an embodiment, includes: preparing dismantling of the calandria; dismantling a reactor pipe installed in the calandria; dismantling the cover assembly that covers the calandria; dismantling the calandria; and dismantling the calandria vault.

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 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 invention relates to a method for decontaminating a radioactively contaminated metal surface, wherein the metal surface is brought in contact with a decontamination solution, which comprises a complexing agent and a transition metal. The invention further relates to such a decontamination solution and to the use thereof to decontaminate a metal surface.

Disclosed herein are embodiments of an extractant that can be used for chromatographic isolation of radioisotopes and/or metal species. The extractant can be combined with a support medium to provide an extractant composition that selectively and efficiently binds particular radioisotopes and/or metal species. Also disclosed herein are embodiments of a method for using the disclosed extractant embodiments, as well as embodiments of a method for making the extractant and extractant composition.