The electrolytic recovery of uranium from Vitro leach liquor by means of ion exchange membranes /

The investigation of the electrolytic precipitation of uranium from a sample of acid leach liquor in an ion exchange membrane cell has been conducted on leach liquor from the Vitro Co. This leach liquor can be treated by the above means to precipitate essentially all the uranium and simultaneously to produce additional acid which may be used for further leaching.

The solvent-solvent extraction of uranium from sulfuric acid solutions with oil soluble amines /

Fifty oil soluble amines were screened for possible use as extractants for uranium from sulfuric acid solutions. The most promising of these were studied further to obtain the optimum conditions for operation of such a process. Kerosene was used as the diluent.

The optical properties of ten metal cupferrates /

"U.S. Atomic Energy Commission Contract AT(29-1)-1106."

Plexiglas reflected assemblies of plutonium /

This report contains a compilation of critical extrapolations of subcritical neutron multiplication measurements made on assemblies of plutonium metal tamped with Plexiglas.

Coating beryllium with electroless nickel /

"U.S. Atomic Energy Commission Contract AT(29-1)-1106."

The alpha angle adjuster /

A device called the alpha angle adjuster has been developed by the Rocky Flats Plant, Division of the Dow Chemical Company, that enables linear measurements to be made perpendicular to almost any curved surface.

Sorption of chromate by Dowex 1 /

A laboratory investigation was made to explore the use of Dowex 1 for the removal of chromate ion from neutral solution. It was found that chromate ion is sorbed by Dowex 1 under a variety of conditions.

Preparation of pure americium /

"U.S. Atomic Energy Commission Contract AT(29-1)-1106."

Ammonium diuranate precipitation with anhydrous ammonia /

Ammonium diuranate has been precipitated from nitric acid solutions by the addition of anhydrous ammonia on both laboratory and production scales. This process produced more dense and more rapidly filtered precipitates than those formed by the addition of aqueous ammonia or slurried calcium hydroxide. The filtrates from the anhydrous ammonia process were lower in uranium content than those obtained by the addition of the other reagents. Processing equipment and precipitate characteristics are discussed.

Volumetric analysis of uranium metal /

A precise and rapid method for the volumetric assay of uranium metal has been developed. The method consists of dissolving a weighed sample in an aqueous mixture of hydrochloric, sulfuric, and fluosilicic acids. The resulting uranium solution is titrated without a subsequent reduction step.

Purification of americium chloride solutions by mercury cathode electrolysis /

A process has been developed for the removal of chromium, copper, iron, manganese, nickel, lead, tin, and zinc impurities from an acid aqueous solution of americium chloride using a mercury cathode cell operating at 5-10 amperes and 16-18 volts. The americium is not affected. The process may also be used to remove other impurity elements.

Plutonium plexiglas assemblies.

"U.S. Atomic Energy Commission Contract AT(29-1)-1106."

Investigation of salts for use in uranium metal heat-treating baths /

Numerous salts were considered for uranium metal annealing baths. Tests on melting point, solubility, corrosion stability, and hydrogen concentration were conducted on the salts which appeared to be the most feasible for this operation under existing conditions.

The impurity analysis of americium solutions /

A solution d-c arc method has been developed for the impurity analysis of americium solutions which are from 3-5 Molar in ammonium thiocyanate.

Research and development quarterly progress report for ...

"RFP [Series]" ; "UC [Series]"