摘要:
A method of passivating the surface of particulate uranium oxides is disclosed comprising a process of continuously contacting uranium oxide particles with an oxygen containing and cooling counter flowing gas stream. The treatment produces a protective surface which inhibits subsequent oxygen chemisorption of the particulate uranium oxides.
摘要:
A process for controlling the oxidation reaction of oxides of uranium and fixing the ratio of oxygen to uranium in uranium oxide compounds by means of a passification process, and the stabilized uranium oxide compounds produced therefrom. The method is especially useful in the production of uranium oxide fuel for nuclear reactors.
摘要:
This invention provides an improved process of preparing UO.sub.2 powder from poor quality, partially oxidized powder containing organic and inorganic impurities. The process is illustrated in the flow chart of FIG. 1 which includes the steps of (a) oxidizing a uranium-containing scrap also containing inorganic and cationic organic impurities; (b) solubilizing, typically with nitric acid, the uranium contained in the oxidized scrap to produce uranyl nitrate; (c) solvent extracting the solubilized product of step (b) to remove cation impurities to provide a purified uranyl nitrate solution; (d) precipitating the purified uranyl nitrate with ammonia to form ammonium diuranate powder; and (e) calcining and passivating the ammonium diuranate powder to produce UO.sub.2 powder; and optionally (f) forming the UO.sub.2 powder of step (e) into pellets and sintering the formed pellets to produce sintered UO.sub.2 pellets.
摘要:
Technetium-99 is quantitatively determined in samples containing uranium using extraction chromatography to remove uranium which otherwise interferes in detecting technetium-99 in low concentrations.
摘要:
A mixture of fine and cohesive powders is blended to complete homogeneity in a nuclear-safe bubbling-bed fluidized bed blender having an improved fluidizing grid. The blender includes a generally vertically-oriented slab-shaped, nuclear-safe mixing vessel having a fluidizing grid disposed at one end of the vessel. The fluidizing grid comprises a linear array of generally downwardly-directed, pyramidal-shaped hoppers each having walls converging into a conically-shaped opening. A plurality of ball valves are employed, one such valve being disposed at the bottom of each hopper. The rotary closure member of each of the ball valves includes a first set of gas orifices for directing a flow of fluidizing gas upwardly in a divergent swirl-shaped pattern along the walls of each of the hoppers. In one embodiment a second set of fluidizing gas orifices for directing a flow of fluidizing gas downwardly into the apex of each of the hoppers is also provided. During blending, fluidizing gas is supplied to the first set of orifices, or to a combination of the first and second sets of orifices, in an amount sufficient to cause bubbles of fluidizing gas to rise through the mixture of powders and emerge from the top surface of the powders until a homogeneous blend of powders is achieved.
摘要:
The present invention relates to a process of decontaminating zirconium-based alloy claddings tubes used in nuclear reactor fuel rods. The process involved the use of a permanganate in a dilute acid solution. The process renders the alloy suitable for uncontrolled release into a non-radioactive environment.
摘要:
A fugitive binder composition for compression molding uranium dioxide nuclear fuel comprising the reaction product of a strongly alkali water solution of a diamine and oxalate ions with uranium oxide which is free of carbonates and carbamates, and having the formula:[.sup.+ NH.sub.3 (CH.sub.2).sub.2 NH.sub.3.sup.+ ][UO.sub.2 (C.sub.2 O.sub.4).sub.2 (H.sub.2 O).sub.2 ][.sup.+ NH.sub.3 (CH.sub.2).sub.2 NH.sub.3.sup.+ ].
摘要:
A safe analytical technique for determining the concentration amount of dibutyl and monobutyl phosphate degradation products in the TBP-dodecane solvent used in solvent extraction processes. This method of chemical analysis eliminates the use of diazomethane, which is toxic and explosive, thereby providing a safer laboratory technique for routine analyses required to monitor production solvent extraction processes. The solvent sample to be analyzed is spiked with mass labelled, deuterated dibutyl and monobutyl phosphates, which act as internal standards. After adding a silylating agent, bistrimethylsilyltrifluoracetamide, the sample is injected into a gas chromatograph/mass spectrometer, which measures the ratio between the labelled internal standard and the naturally occurring material to obtain a quantitative result.
摘要:
An apparatus for solvent extraction processes utilizing countercurrent flow of streams of an aqueous phase and an organic phase, such as the Purex process for uranium recovery. The invention comprises contouring the fluid passing orifices in the column phase dispersing perforated plates to impede droplet coalescence of the dispersed phase.
摘要:
A method and apparatus for the introduction of second cohesive powders into an improved fluidized bed blender containing UO.sub.2 powder, and for blending such second cohesive powders with the UO.sub.2 powder in the fluidized bed blender. The apparatus comprises an eductor, an improved pressurized vortec mill, a pneumatic conveying system that operates in turbulent flow, and an improved fluidized bed blender. The method and apparatus provide for injection and uniform dispersion of a second cohesive powdered ingredient or ingredients having hydrophobic, hydrophilic or hygroscopic properties in the fluid bed blender adjacent the bottom of the fluidized bed therein during the blending operation, thereby minimizing entrainment of the second powder mixture and providing a homogeneous blend of powders.