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]"

Observations of gamma emissions associated with thorium removal from a U²³³ sample /

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

Recovery and preliminary purification of Americium obtained from waste material /

"Contract AT (29-1)-1106."

Indium seals /

The feasibility of using indium seals for large vacuum bell jars has been investigated. It is shown that such seals can be made; however, use of this type seal for repetitive operations is not recommended.

A study of two commercial film badge services /

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

Volumetric calibration of process vessels using digital computer techniques /

The paper describes a procedure for accurately and speedily calibrating tanks used for the chemical processing of nuclear materials. The procedure features the use of (1) precalibrated vessels certified to deliver known volumes of liquid, (2) calibrated linear measuring devices, and (3) a digital computer for manipulating data and producing printed calibration information. Calibration records of the standards are traceable to primary standards. Logic is incorporated in the computer program to accomplish curve fitting and perform the tests to accept or to reject the calibration, based on statistical, empirical, and report requirements. This logic is believed to be unique.

An analyzer for radioactive gas /

An instrument that can continuously monitor air for tritium has been developed. It utilizes a flow type ionization chamber and a vibrating reed electrometer. A response of double normal background is produced by 9.4 x 10⁻⁵ [mu]c H³/cc air; the presently accepted MPC is 2.0 x 10⁻⁵ [mu]c H³/cc air. Its operation is completely automatic.