Patent classifications
G21F9/304
Dismantling and decontamination system and method of bioprotective concrete of PWR type nuclear power plant
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.
DISMANTLING AND DECONTAMINATION SYSTEM AND METHOD OF BIOPROTECTIVE CONCRETE OF PWR TYPE NUCLEAR POWER PLANT
A dismantling and decontamination system of bioprotective concrete of a nuclear power plant according to an exemplary embodiment includes: a dismantling device for dismantling an in-core instrument installed under bioprotective concrete to form a lower penetrated part of the bioprotective concrete; a decontamination device inserted inside the bioprotective concrete for decontaminating radioactive waste of the inner wall of the bioprotective concrete; a waste receiving device movable through the lower penetrated part of the bioprotective concrete; and a blocking device for blocking the upper opening of the bioprotective concrete to block an outflow of the radioactive dust.
Hazardous waste disposal using salt
A hazardous material storage repository includes a borehole that extends into the Earth from a terranean surface. The borehole includes an entry and a hazardous material storage borehole portion formed in a subterranean salt formation. The repository includes a storage canister positioned in the hazardous material storage borehole portion. The storage canister is sized to fit from the entry through a substantially vertical borehole portion of the borehole, and into the hazardous material storage borehole portion. The storage canister includes an inner cavity sized to enclose nuclear waste material that includes TRansUranic waste.
MAGNESIA CEMENT FOR THE SOLIDIFICATION OF AQUEOUS WASTE
The present invention is directed to a solidified composition and a method of making such solidified composition. The solidified composition may have a lower leachate pH when compared to ordinary Portland cement. The solidified composition may be formed from a slurry comprising magnesium oxide, a salt, and water. Notably, the solidified composition may further comprise one or more actinides. The methods of the present invention are directed to making the aforementioned solidified compositions.