Westinghouse Electric Corporation

Wyoming Mineral Corporation

Thomas J Crossley

John J Wilhelm

Robert D Burack

Fredrick J Klorcyzk

Thomas P Zinge

A nozzle dam for providing a fluid-tight seal across a primary fluid nozzle in the plenum of a nuclear steam generating vessel includes two fluid-impermeable seals, each comprising a circular three-section foldable seal plate covered with a flexible diaphragm and circumferentially encompassed by an inflatable seal member disposable in frictional sealing engagement with the inner surface of the nozzle. The two seal apparatuses are interconnected by a central tubular coupling coaxial with the nozzle and non-rotatably fixed to each seal, the coupling having a quick-disconnect feature operable from outside the nozzle dam. The coupling provides a conduit for inflation of one of the seals. The two seals are also interconnected by four post assemblies to maintain the seal plates parallel with each other, each post assembly including a cylindrical member pivotally movable between a release position and a supporting position, and provided with a slidable encompassing sleeve to lock it in the supporting position. Structure is provided for pressurizing the inter-seal space and monitoring the pressure in that space.

Dual seal nozzle dam and alignment means therefor

A method is disclosed for separating uranium from molybdenum in an aqueous solution. The pH of the solution is lowered to about 1 to about 4 using an inorganic acid such as hydrochloric acid. The carbon dioxide is then removed from the solution which can be done by aeration. The pH of the solution is raised to about 9 in the presence of ammonium ions which result in the precipitation of ammonium diuranate. The precipitated ammonium diuranate may then be filtered or otherwise separated from the molybdenum which remains in the solution.

Method of separating molybdenum from uranium

Disclosed is a method of removing uranium from a slurry containing a water-insoluble molybdate and a Group II element, usually calcium. The pH of the slurry is raised with an alkali metal hydroxide and maintained at a level sufficiently high to solubilize insoluble molybdenum compounds. This will generally require a pH of at least 10 which can be achieved by adding sodium hydroxide. Carbonate ion is then added to the slurry in an amount at least sufficient to precipitate the cation of the insoluble molybdenum compound. And finally, the solid portion of a slurry, which now contains calcium carbonate and sodium uranate, is separated from the liquid portion, which contains a soluble molybdenum compound.

Method of removing uranium from a slurry containing molybdenum

Waste water containing large amounts of fluorides and ammonia and trace amounts of uranium, as is produced during the hydrolysis and ammonium hydroxide treatment of uranium hexafluoride (UF.sub.6) to produce ammonium diuranate (ADU) therefrom, is rendered suitable for cyclic reuse by initially treating the waste water with sufficient lime to precipitate substantially all of the fluorides present in the waste water to a relatively insoluble CaF.sub.2 precipitate, the treated solution is subjected to distillation to drive off ammonia for reuse in the ADU precipitation, the CaF.sub.2 precipitate is separated from the aqueous distilland leaving water with dissolved calcium, the distilland is treated by a cationic ion-exchange material to remove substantially all of the calcium and other cationic metal impurities and the resulting water containing small amounts of uranium, fluoride and ammonia is recycled to react with UF.sub.6 or to be combined with the ammonium hydroxide distillate and then treated with additional concentrated ammonium hydroxide to form a solution of the desired NH.sub.3 content for use in precipitating ADU. This recycling is most important for ecological reasons, and for cost improvement, as well as health and safety purposes.

Growing community of inventors

Littleton, CO, United States of America

Thomas J Crossley