Patent classifications
G21F9/162
PROCESS FOR IMMOBILIZING HAZARDOUS WASTE
A process for immobilizing hazardous waste includes mixing the hazardous waste with a non-swelling clay, a cementitious binder and, optionally, water, and allowing the resulting mixture to set to an immobilized waste material. The process can also include dispersing the hazardous waste in the non-swelling clay to form a dry mixture, mixing the cementitious binder and, optionally, water with the dry mixture to produce a plastic mixture, and allowing the plastic mixture to set to the immobilized waste material.
CONTAINER FOR STORAGE OF MOLTEN MATERIAL FROM AN INDUSTRIAL FACILITY AND METHOD OF MANUFACTURING SAME
A container for storage of molten material from an industrial facility, and method of manufacture thereof, is provided to maximize internal volume of the container while providing structural stability. The container includes walls having rounded convex-shaped edges at each wall junction. A first head is connected to the walls at a first end of the container, and a second head closes the second end of the container. The second head is connected to the walls at a second end of the container. Corners are defined at the intersection of the walls with the first head and second head at the first end and the second end respectively. A first flange is connected to the first head to receive molten material, and the first head is shaped as a tapered shoulder to smoothly transition from the first flange to the junction of the walls.
SILICOTITANATE MOLDED BODY, PRODUCTION METHOD THEREOF, ADSORBENT FOR CESIUM AND/OR STRONTIUM COMPRISING SILICOTITANATE MOLDED BODY, AND DECONTAMINATION METHOD FOR RADIOACTIVE WASTE SOLUTION BY USING ADSORBENT
Provided are a silicotitanate molded body having high strength and reduced generation of fine powder, a production method thereof, an adsorbent comprising the silicotitanate molded body, and a decontamination method of radioactive cesium and/or radioactive strontium by using the adsorbent. The silicotitanate molded body comprises: crystalline silicotitanate particles that have a particle size distribution in which 90% or more, on volume basis, of the particles have a particle size within a range of 1 m or more and 10 m or less and that are represented by a general formula of A.sub.2Ti.sub.2O.sub.3(SiO.sub.4).nH.sub.2O wherein A represents one or two alkali metal elements selected from Na and K, and n represents a number of 0 to 2; and an oxide of one or more elements selected from the group consisting of aluminum, zirconium, iron, and cerium.
Method of handling radioactive solutions
The invention relates to the field of environmental protection, more specifically to the field of processing radioactive waste, and can he used for the safe and effective handling of a large quantity of liquid radioactive waste of various activity levels that has been formed as the result of decontaminating protective equipment of boxes and chambers, and makes it possible to decrease the volume of stored waste by solidifying same and incorporating same into a ceramic matrix. For this purpose, radioactive solutions after decontamination of surfaces of protective equipment are evaporated as alkaline and acidic solutions containing sodium hydroxide, potassium permanganate, oxalic acid, and nitric acid until a solid residue forms, and are calcined, and the calcinate is mixed with components of a fusion mixture containing oxides of titanium, calcium, iron (III), zirconium, and manganese (IV) and aluminum in a specified ratio, and fused.
Process for the removal of 99Tc from liquid intermediate level waste of spent fuel reprocessing
Provided herein is a process for removal of .sup.99Tc from liquid intermediate level waste (ILW) of spent fuel reprocessing including the steps of: adding HNO.sub.3 to ILW till the pH is 2 to destroy the carbonates, transferring the ILW derived of carbonates to a tank containing mild steel wool (msw) for 4 to 48 hrs, subjecting the ILW and MS Wool to the step of separation, discharging the supernatant solution free of .sup.99Tc and retaining the corrosion products (goethite(FeOOH/magnetite), subjecting the said corrosion products to the step of vitrification, and storing the said vitrified .sup.99Tc bearing waste.
METHOD OF HANDLING RADIOACTIVE SOLUTIONS
The invention relates to the field of environmental protection, more specifically to the field of processing radioactive waste, and can he used for the safe and effective handling of a large quantity of liquid radioactive waste of various activity levels that has been formed as the result of decontaminating protective equipment of boxes and chambers, and makes it possible to decrease the volume of stored waste by solidifying same and incorporating same into a ceramic matrix. For this purpose, radioactive solutions after decontamination of surfaces of protective equipment are evaporated as alkaline and acidic solutions containing sodium hydroxide, potassium permanganate, oxalic acid, and nitric acid until a solid residue forms, and are calcined, and the calcinate is mixed with components of a fusion mixture containing oxides of titanium, calcium, iron (III), zirconium, and manganese (IV) and aluminum in a specified ratio, and fused.
Process for the Removal of 99TC from Liquid Intermediate Level Waste of Spent Fuel Reprocessing
Provided herein is a process for removal of 99Tc from liquid intermediate level waste (ILW) of spent fuel reprocessing including the steps of: adding HNO.sub.3 to ILW till the pH is 2 to destroy the carbonates, transferring the ILW derived of carbonates to a tank containing mild steel wool(msw) for 4 to 48 hrs, subjecting the ILW and MS Wool to the step of separation, discharging the supernatant solution free of 99Tc and retaining the corrosion products (goethite(FeOOH/magnetite), subjecting the said corrosion products to the step of vitrification, and storing the said vitrified 99Tc bearing waste.
Method for vitrification of waste
A method for vitrifying waste to prevent the formation of molybdate secondary phases includes forming a feed mixture that includes the waste, a source of vanadium, and at least one of glass frit or glass forming chemicals and vitrifying the feed mixture in a melter to produce a glass product that includes the waste.
METHODS OF USE AND MANUFACTURE OF SILVER-DOPED, NANO-POROUS HYDROXYAPATITE
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.
METHOD AND APPARATUS USING FOAMED GLASS FILTERS FOR LIQUID PURIFICATION, FILTRATION, AND FILTRATE REMOVAL AND ELIMINATION
A method of disposing of waste material in a waste stream, including positioning a porous foamed glass member characterized by an open-cell interconnected pore network in contact with a volume of liquid to be purified and removing an amount of an undesired material from the volume of liquid.