"This is a bibliography of journal articles relating to beryllium oxide. Sources consulted include; Chemical Abstracts, 1951-1955; Physics Abstracts, 1951-1955; Industrial Arts Index, 1955-Jan, 1957; and the library card catalog. Starred articles are available in the library.

In order to test the effect of chromate ion on the corrosion of Zircaloy-2 a 0.04 m uranyl sulfate solution (enriched) containing added acid, copper sulfate and 557 ppm Cr (VI) was autoclaved with rocking at 280 C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the a rate of consumption of oxygen was 9.9 mpy at a power density of 4.9 w/ml. It is indicated by comparison with a previous corrosion study under LITR radiation that the presence of Cr (VI) had no significant effect on the radiation corrosion of Zircaloy-2 by enriched uranyl sulfate solutions. However, the data are not conclusive and may be interpreted as showing a low corrosion rate for a limited period (i.e. a short term inhibition) followed by a correspondingly rapid corrosion.

In order to test the effect of chromate ion on the corrosion of Zircaloy-2, a 0.04 m uranyl sulfate solution (enriched) containing added acid, copper sulfate and 557 ppm of Cr (VI) was autoclaved with rocking at 280 degrees C for about eight days in the HB-5 facility of the LITR. The average corrosion rate established by the rate of consumption of oxygen was 9.9 mpy at a power density of 4.9 w/ml. It is indicated by comparison with a previous corrosion study under LITR radiation that the presence of Cr (VI) had no significant effect on the radiation corrosion of Zircaloy-2 by enriched uranyl sulfate solutions. However, the data are not conclusive and may be interpreted as showing a low corrosion rate for a limited period (i.e. a short term inhibition) followed by correspondingly rapid corrosion.

Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1955, activities, organizational leadership, and other information about scouting programs.

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Below Richland, Washington there is a gradual decrease in the concentration of beta particle emitters in the Columbia River water. The concentration of alpha particle emitters in Columbia River water averages 5 X 10⁻⁹ μl/ml at all locations. The activity of alpha particle emitters in mud samples was less than the detection limit of 3 x 10⁻⁶ μl/gm; the average activity density of beta particle emitters approximates those reported for the previous quarter.

From introduction: "This investigation was undertaken with the general objective of determining whether uranium core could be sheathed with aluminum by an extrusion-cladding process. The ultimate objective of this work was to determine the feasibility of extrusion cladding flat plates of uranium."

The major design features, nuclear characteristics and performance data for a nuclear fueled central station power plant of 75,000 kw net capacity are presented. The heat source is a Na cooled graphite moderated reactor. The design of the reactor takes full advantage of the experience gained to date on the Sodium Reactor Experiment (SRE); the plant described here is a straightforward extension of the smaller experimental SRE, which is now under construction. The fuel elements are made up of rod clusters and the moderator is in the form of Zr canned graphite elements. The performance of the reactor has been based on conservative temperatures and coolant flow velocities which result in a plant with "built-in reserve." Thus, as experience is gained and anticipated improvements in reactor fuel elements and construction materials are proven, the performance of the plant can be increased accordingly. Two reactor designs are described, one for operation with slightly enriched U fuel elements and the other for operation with Th--U fuel elements. The associated heat exchangers, pumps, steam, and electrical generating equipment are identical for either reactor design. An analysis of turbine cycles describes the particular cycle chosen for initial operation and discusses a method by which …

The Uranium Recovery Plant, over the life of the operation, will be required to attain maximum recovery of stored uranium and to produce aqueous waste in a volume equivalent to the volume of stored uranium waste which, after acidification, constitutes the feed stream for the process. Due to variations in the composition of the feed stream, the waste stream does not consistently have a volume equivalent to the volume of the stored metal waste. This variation volume equivalence impedes tank farm scheduling because of the necessity for return of the process waste to underground tanks made available by the recovery operations. A plant test, using nickel ferricyanide to remove Cs-137 and Sr-90 from the Uranium Recovery Plant wastes has been completed and this memorandum has been prepared to summarize and report the results obtained from this test.

Report presenting an investigation of 57 experimental tubular designs embodying adjacent fuel-rich and air-rich regions and axial staging of the fuel introduction at simulated high-altitude conditions. Results regarding the development of pilot, development of secondary-air admission sleeve, development of final configuration, and performance of best configuration are provided.

This document discusses studies of the behavior of uranium metal as a fuel element which previously have been hampered by the lack of understanding of the nature of radiation damage to the crystal structures. With the aid of the double crystal x-ray spectrometer, samples from irradiated fuel elements which had receive total exposure of 150 MWD/T and 1,000 MWD/T were studied and gross radiation damage was not present. Although these findings are of a preliminary nature, they are well in agreement with theoretical calculations in which the equilibrium concentration of displaced atoms at temperatures above 200{degrees}C would be extremely low. Assuming this to be the case, most of the crystallographic imperfection induced by pile radiations must have been annealed out of the metal studied. On the basis of this work it would seem quite likely that some fundamental facts about the nature of radiation damage could be learned by keeping the temperature low. This production test is designed so as to give information regarding the crystal structure damage where the uranium temperature during irradiation and post-irradiation operations is kept below 35{degrees}C.

This report, dated March 22, 1954 details work procedures for the 200- West Area at HAPO. Topics discussed include emergency procedures, safety and housekeeping practices, policies and procedures, instruments and equipment located at the 622 tower, instruments and equipment located offsite, observational procedures, form entries, and card punching, and weather forecasting.

Annual report submitted by the Boy Scouts of America to Congress describing highlights from 1951, activities, public relations, programming, finance, organizational leadership, and other information about scouting programs.

Report presents the results of a flight investigation conducted on a typical high-wing personal-owner airplane to determine the effect of control centering springs on apparent spiral stability. Apparent spiral stability is the term used to describe the spiraling tendencies of an airplane in uncontrolled flight as affected both by the true spiral stability of the perfectly trimmed airplane and by out-of-trim control settings. Centering springs were used in both the aileron and rudder control systems to provide both a positive centering action and a means of trimming the airplane.

This report follows the study of the oxidation of plutonium III and IV to the plutonyl state.

This report discusses methods for preparing thin films of plutonium on metallic disks, which are used for alpha energy analysis, fission counting, and preparation of geometry standards in ordinary counting. Various methods of preparation were tested and analyzed, but electrodeposition was the most effective method. Deposition was then tested, but the yields were "somewhat erratic".

The third report in a series of five that present unanalyzed pressure data obtained in tests of five full-scale propellers with NACA 16-series blade sections. Pressure distributions on the blade sections were measured under operating conditions to determine the aerodynamic characteristics of each blade section. This particular report presents information for nine radial stations of the NACA 10-(3)(090)-03 propeller.