From summary: The object of the study was to determine if the heavy metal ions within the concentration ranges normally found in pile cooling water were responsible for corrosion of aluminum.

Abstract: "Laboratory production of an explosion between UNH and "red oil" under calcination conditions has been accomplished. Attempted production of a vapor phase explosion was unsuccessful below 150-160 C. Since such severe conditions are necessary to obtain an explosive reaction, it appears that present Purex plant design is adequate to avoid explosive conditions."

Report discussing several experiments investigating the effect of radiation on metals, specifically on intermetallic diffusion, mechanical properties of 347 stainless steel and electric resistance of 347 stainless steel.

Abstract: "A novel procedure employing ion exchange resins was developed to separate chromate ions from hydrogen peroxide, permitting, permitting the subsequent analysis of peroxide to determine its decomposition in sodium chromate solutions. At high pH's, peroxide was absorbed anionically on the ion exchange resins along with chromate. By selecting a resin which would be effective at nearly neutral conditions, chromate was satisfactorily separated from peroxide. It was found that the rate of peroxide decomposition in slightly alkaline sodium chromate solutions was dependent on temperature, pH, aeration, and chromate concentration. No significant effect on decomposition was caused by visible light."

It is the purpose of this document to outline a proposed addition to the previously considered clean-up systems as a possible solution for the maintenance of high purity water. A cyclone separator system has been devised in conjunction with the water clean-up of a high temperature recirculating reactor cooling system. By utilizing such a cyclone separator system, a high quality water can be obtained in a primary coolant system made up of carbon steel components without excessive clean-up costs.

This report summarizes the research and development work carried out during June, July, and August, 1959, for Budget Activity 2790- Separations Development for Non-Production Reactors. The effort on Activity 2790 - Separations Development for Non-Production Reactors. The effort on Activity 2790 will enable Hanford to begin reprocessing in January, 1962, the fuel elements from power reactors which employ depleted or slightly enriched uranium fuels.

The feasibility of rectified absorption for the recovery and purification of HD from H2 streams has been investigated. The absorbent considered was liquid nitrogen at 78 (degrees) K. The process appears to present no major engineering or operation problems. Cost calculations indicate that the process may be economically competitive with other processes. Process design was based on an estimated separation factor of 1.25 between H2 and HD in this system. Experimental work has been undertaken to check the validity of this estimate and to investigate the possibility of using other absorbents such as hydrocarbons and fluorocarbons.

Using ferrous ion in the presence of fluoride for reducing uranium(VI) to the four state, the salt calcium uranium (IV) fluoride can be precipitated from uranyl nitrate solutions. X-ray studies have shown that the precipitate is a true double salt and not a mixture of the two insoluble fluorides of calcium and uranium. The salt settles rapidly and can be either filtered or centrifuged. Waste losses during precipitation and washing were on the order of 2.0 and 0.4 per cent, respectively. These waste losses are not primarily solubility losses. During filtration of the supernates some fines were not removed by the sintered glass filter, and post-precipitation was also noticed. The hydrated salt contains approximately one mole of water which can also be removed without hydrolysis by drying at 250 C in an atmosphere of deoxygenated argon. Dry calcium uranium fluoride prepared in this manner is free flowing with a bulk density of about 1.25 g/cm³.

A study and tests of the feasibility and best method of reaming rear face Parker fittings has been made. Flow increase of 8 percent, based on maintaining the same front header pressure, can be obtained at B, D, and F reactors by reaming the rear Parker fittings to .610 inch and using existing rear face hardware. Tests indicate mechanical strength will not be significantly reduced, high frequency vibration will not be increased, and that methods of reaming are available.