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The July, 1958 monthly report for the Chemical Processing Department of the Hanford Atomic Products Operation includes information regarding research and engineering efforts with respect to the Purex and Redox process technology. Also discussed is the production operation, finished product operation, power and general maintenance, financial operation, engineering and research operations, and employee operation. (MB)

This report, for July 1957 from the Chemical Processing Department at HAPO, discusses the following; Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; and employee relations.

A study was made to determine the magnitude of the velocities existing in the various slurry pumps currently in use and to determine possible methods of reducing the velocities in order to obtain longer life. The maximum velocities of the lOOA, 200A, and 300A pumps are between 39 and 53.6 fps with the exception of the lOOA absolute discharge velocity which is 80.6 fps. For large slurry pumps, it is recommended that lower speeds be used in order to reduce the impeller relative velocities. (auth)

The differences in the sizes and shapes of crystals formed during four common types of thermal gradient mass transfer experiment are discussed These difference are illustrated with photograped for each case considered. A mechanism is advanced to accoutn for the of mass transfer experiment. Based on an idealized icting the stabe under various experimental conditions. Numberical n graphical form. (auth)

Evidence is presented that the hot-zone attack of nickel-base alloys in contact with fused fluorides occurs by a grain-boundary diffusion process. Predictions based on tbe grain-boundary diffustion model are shown to copmpare favorably with existting data. Certain anomalies are pointed out with regard to the corrosion of Inconel by Fuel No. 20 (NaF-UF/sub 4/-ZrF/sub 4/) and tests which would lead to a better understanding of fused-salt corrosion are outlined. (auth)

The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 6OO deg F. Quenching from 6OO deg F or above gives high impact strength, as does removal of hydrogen by hightemperature vacuum aanealing. The evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilbrium pressure of hydrogen in zirconium the microstructure, and the effects of hydrogen and heat treatment on the mechanical properties of zirconium are discussed. (auth)

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A previous investigation concerned with liquid-core fuel elements and the materials from which they could be constructed revealed tht an alloy of U--5 wt. % Nb had considerable promise as container material. Results are given from a further investigation of this alloy, as well as another containing 10 wt. % Nb, to determine the time and temperature limits within which tbe oxide layer remains protective, the factors which hasten or delay the breakdown of the film, and the mechanism whereby the film deteriorites, (auth)

Two methods for extrusion cladding were investigated and evaluated. In the coaxial method, the component parts of the extrusion assembly are concentric, and the fuel plate moves in the same direction as the hydraulicpress ram. In the right-angle method, the fuel-plate metion is perpendicular to that of the ram. Ribbed sheaths of aluminum were extruded satisfactorily on 3-in.-wide uranium plates in lengths up to about 10 ft. Lowest extrusion pressures were achieved with the most streamlined designs of mandrel tips, using flatfacod shear dies. Good results were obtained with billet and die temperatures of about 1050 deg F, at extrusion speeds up to 60 ipm. Extrusion pressures were 25,000 to 60,000 psi. End-cladding procedures were developed which involvod attaching end plates machined from aluminum powder-metallurgy products (12 to l8 wt. % Al/sub 2/O/sub 3/) to the core by means of T-shapod joints, and cladding the entire assembly with aluminum. Excellent bonds were achieved, on uranium as well as on the end plugs. The median values obtained by stud weld tests were 26,000 psi for uranium, and 12,000 psi for the end plugs. The importance of proper tool alignment and avoidance of imbalance of forces caused by pressure differentials within the …