Site ``W`` description (open access)

Site ``W`` description

This site description of the Hanford Reservation from February 1943 gives size, topography, geology, population, water supply, railroad, highway, power, meteorological, and valuation information. Maps are included.
Date: February 15, 1943
Creator: Grady, J. A.
System: The UNT Digital Library
Weekly progress report -- Technical Section for period ending June 12, 1943 (open access)

Weekly progress report -- Technical Section for period ending June 12, 1943

Progress was reported from the 300, 100, and 200 Areas. It covered the X pile, aluminium corrosion, graphite purity, fuel element fabrication, bismuth phosphate extraction and decontamination processes, waste disposal from bismuth phosphate processing, control rod systems for Site W, shielding problems at the Site W separation plant, fuel element failure detection, power distribution in the Clinton pile, reactor instrumentation for Site W.
Date: June 15, 1943
Creator: unknown
System: The UNT Digital Library
Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending May 15, 1943 (open access)

Metallurgical Laboratory, Chemical Research - Radiation Chemistry, Report for the Month Ending May 15, 1943

Technical report that information has bee obtained on the effect of beta and gamma radiation on the electrical resistance of insulating materials The results are summarized. The recovery to original resistance values has been measured. In general, the initial rate is rapid for the first few hours; the rate then decreases sharply. Certain samples show evidence of complete recovery. Effects on mechanical properties of several plastics has also been studied. Data on gas evolution from several organic materials including those suggested by the physiological shield have been extended to include both beta and deuteron bombardments. Samples of "Press-wood" are being evaluated. The effect of current on the H2O2 production in water containing I- has been studied at several I- concentrations. Water contain-dissolved CO2 shows the presence of oxidant (presumably H2O2). H2O2 has been produced by recoil protons from the scattering of fast neutrons in de-oxygenated water. Radioactive solutions do not greatly affect the applicability the glass electrode providing the electrode is thoroughly washed with distilled water before immersion in the standard buffer solution.
Date: May 15, 1943
Creator: Franck, J.
System: The UNT Digital Library
Physical Properties of Uranyl Sulfate Solutions (open access)

Physical Properties of Uranyl Sulfate Solutions

Abstract: Measurements are reported of the solubility of uranyl sulfate in water at several temperatures, of the density of uranyl sulfate solutions as a function of concentration, of the variation of density of uranyl sulfate solutions of three different concentrations over a temperature range from 0[degree]C. to about 93[degree]C., and of the pH of uranyl sulfate solutions as a function of concentration as well as of temperature. The pH measurements were taken on uranyl sulfate samples prepared in several different ways and some conclusions are drawn as to the purity of theses samples.
Date: December 15, 1943
Creator: Helmholz, Lindsay. & Friedlander, G.
System: The UNT Digital Library