4454results about "Radioactive decontamination" patented technology

Disclosed is a method of excavating large quantities of non-homogenous radioactive contaminated waste, desirably without releasing radioactive contaminated dust or exposing personnel to its hazards. The excavation of buried waste is performed in the presence of a suppression fluid that coats the waste and captures and retains particles so that they do not become airborne. Use of this suppression fluid technique allows larger mechanized excavation equipment to be used to perform the work. This keeps workers away from the waste. The waste is excavated and placed inside large steel boxes, such as a roll-off box, by the excavator. The suppression fluid covers the waste in the boxes and prevents particulate emissions from the waste.

A solid phase mixed solvent polymer, compositions and methods for removing and retaining solvated organic compounds and inorganic ions from water, wastewater, superficial and ground water, soil and other environmental sources, a soil amendment and method resulting from adhesively coating the polymer onto sand along with at least one ion exchange material, and methods for the containment, reduction, and prevention of organic leaching from soils, agricultural, industrial, and commercial environments, and in particular, sports and athletic turf facilities such as golf courses where pesticides are frequently applied.

A method for producing a surface-activated crystalline titanium oxide product having a high adsorptive capacity and a high rate of adsorption with respect to dissolved contaminants includes the steps of preparing a titanium oxide precipitate from a mixture comprising a hydrolysable titanium compound and heating the precipitate at a temperature of less than 300° C., without calcining the precipitate. Preferably, the titanium oxide product includes crystalline anatase having primary crystallite diameters in the range of 1-30 nm. The surface-activated crystalline titanium oxide product is used in methods to remove dissolved inorganic contaminants from dilute aqueous streams by suspending the product in an aqueous stream or by filtering an aqueous stream through a bed of the product. In another method, a hydrolysable titanium compound is added to an aqueous stream so that titanium oxides form as a co-precipitate with dissolved contaminants within a bed of particulate material.

A method of separation and recovery of elements from radioactive liquid wastes, includes a step of bringing into contact a high-level radioactive liquid waste containing separation target elements including Americium, Curium, Zirconium, Molybdenum, Palladium and rare earth elements with solid absorbent containing organophosphorus compounds so that the separation target elements are absorbed in the solid absorbent, a step of bringing into contact the solid absorbent with an acidic solution containing diethylenetriaminepentaacetic acid so that Americium, Curium, Zirconium, Molybdenum, Palladium and heavy rare earth elements are eluted from the solid absorbent, and a step of bringing into contact the solid absorbent underwent the first elution step with water or dilute nitric acid so that light rare earth elements are eluted from the solid absorbent. With the method, elements, which include Americium, Curium, Zirconium, Molybdenum, Palladium and rare earth elements, are efficiently and economically separated and recovered from the radioactive liquid waste.

This invention relates to the production and use of encapsulated and / or concentrically-constructed fertilizer or bioremediation granules such as, for example, granules of 0.5 mm to 10 mm in diameter constructed so that there are at least two components to the granule including a core with a surrounding capsule or a core with one or more concentric layers that are distinguishable from the core with respect to nutrient content, density, hardness, solubility, composition, microbial content and permeability, as in permeability to odors or the permeability of nutrients that might volatize to the atmosphere or leach into the soil. The basic idea was to create a method for manufacturing and using fertilizer granules, which incorporate multiple concentric layers or a core plus an encapsulating outer layer.

A method of measuring a parameter of a landfill including a cap, without passing wires through the cap, includes burying a sensor apparatus in the landfill prior to closing the landfill with the cap; providing a reader capable of communicating with the sensor apparatus via radio frequency (RF); placing an antenna above the barrier, spaced apart from the sensor apparatus; coupling the antenna to the reader either before or after placing the antenna above the barrier; providing power to the sensor apparatus, via the antenna, by generating a field using the reader; accumulating and storing power in the sensor apparatus; sensing a parameter of the landfill using the sensor apparatus while using power; and transmitting the sensed parameter to the reader via a wireless response signal. A system for measuring a parameter of a landfill is also provided.

A combination of acid zirconium phosphate and alkaline hydrous zirconium oxide are utilized as ion-exchange materials, for example, in sorbent dialysis. The combination provides for dialysate regeneration while maintaining constant and controlled levels of Na+, HCO3−, and pH.

A method and device for filtration and / or purification of fluids water or other solutions containing microbiological and chemical contaminants, such as fluids containing metals, water treatment chemicals, reactive chemicals and microorganisms, where the fluid is passed through a composite material composed of fluid treatment media with or without a binder matrix in which the filtration media, binder, or support structures, or a combination thereof contains a surface treatment.

The invention discloses a method for treating radioactive wastewater. The method for treating the radioactive wastewater comprises the steps of firstly carrying out reverse osmosis treatment on the radioactive wastewater, then enabling the radioactive wastewater to enter a continuous electrodeionization unit to be treated, and further removing radionuclide so as to enable treated wastewater to reach discharge requirements; and respectively filling different mixed ion exchange resin in a plain water chamber and a thick water chamber in a continuous electrodeionization membrane stack of the continuous electrodeionization unit, wherein mixed ion exchange resin filled in the plain water chamber comprises, by volume ratio, 30%-60% of strong-acid cation exchange resin, 40%-60% of strong-base anion exchange resin, and 0%-30% of weak-base anion exchange resin, mixed ion exchange resin filled in the thick water chamber comprises, by volume ratio, 20%-50% of strong-acid cation exchange resin, and the balance strong-base anion exchange resin. A weak dissociation polymer portion is used for improving selectivity of continuous electrodeionization membrane stack to trace amount radionuclide, radionuclide with extremely concentration can be effectively removed, and the method for treating the radioactive wastewater ensures that the final discharged water satisfies the discharge requirements.