The following report is based on the observations made during a visit to the Oak Ride National Laboratories of their Redox Pilot Plant equipment.

Abstract: "The purpose of this investigation is to determine the extent to which zirconium exhibits delayed failure (static fatigue) as caused by a combination of absorbed hydrogen and applied stress. Both notched and unnotched specimens of unalloyed zirconium and Zircaloy-2 are being initially hydrogenated to 200 ppm by means of a modified Sieverts apparatus, and delayed failure studies are proceeding at room-temperature. Thus far only preliminary data on unnotched, unalloyed zirconium are available; at the 200 ppm hydrogen level, this material appears to be relatively insensitive to delayed failure at room-temperature."

This report follows the study of the properties of eutectic uranium-chromium alloy which is of interest in the Dow-Detroit Edison power reactor. The reactor is described in this report, as well as the casting of alloy, shrinkage measurements during solidification, density measurements, microstructures and macrostructures, mechanical properties, and specific heat data.

Summary: "Criticality was considered impossible in any contingency encountered in practice under either of the following conditions which include no safety factor: (a) In any isolated cylinder not more than 5 in. in disruptor, if the total amount of U235 present does not exceed 7.5 Eg. (b) In an isolated vessel of any shape and size, if the total amount of U235 present does not exceed 880 g. An "isolated" vessel is one which does not "see" more than 0.1 [...] other vessels containing fissionable material."

Thesis describing a research conducted to extend observations on nuclear energy levels and how they effect the nucleus itself, and an investigation on the gamma rays associated for the even-even isotopes and to obtain additional data for the oddmass neclei in the hope that more regularities will become apparent for that class of nuclides.

Abstract: Uranium ore deposits on two exposed rims and past production records of tonnage and grade indicate an exploration program is justified in the Oak Springs area. A minimum of 24,000 feet of core drilling is recommended with a maximum of 75,000 feet to be based on favorability as determined by subsurface studies.

Abstract: During the summer of 1955, two test holes were drilled into the Triassic Chinle Formation in the Lukachukai Mountains near Cove, Arizona, to obtain geologic information. Brief airborne and ground reconnaissance was made of Triassic outcrops near Cove. No anomalous radioactivity was found in the test holes, but chemical tests showed concentrations of heavy metals in conglomerate lenses in the Chinle Formation. Channel sandstones in the middle part of the Petrified Forest Member appear to be the most favorable for mineralization. The Shinarump Member, here underlain by a permeable unit, and occurring at depths greater than 500 feet, appears less promising for uranium exploration.

This report analyzes the High-Energy Electrostatic Plasma Gun, which is to be used for propulsion.

Abstract: "Theoretical and experimental results of the effect of gamma moderation are described. A 6.7-fold enhancement factor was obtained with a 1/8-in. - thick sodium-iodide crystal when using gamma moderation and a Co-60 gamma source. A counter was designed and built to make the most use of gamma source. A counter was designed and built to make the most use of gamma moderation. The results indicate that this counter can be made energy independent over a wide region. Though the cost of the counter is about 1/3 that of a 1-in, -diam, 1-in. -thick sodium-iodide crystal plus photomultiplier, the counting efficiency for gammas such as Na-24 is over two times greater."

Technical report describing the investigation of the short-lived activities produced in oxygen compounds by irradiation with pile neutrons. The most prominent of these activities in cooling water is a beta and gamma emitting activity of about 8 second half-life. Because of its production by epicadmium neutrons it was believed to be the 8 second N16 produced in the pile by n,p on O16. The identification has been accomplished and it is established that the 8 second activity is N16. Part 2 of the report deals with the determination of the recoil range of the Al28 atoms formed by pile n,p reaction on Al27.

Report documenting the suitability of the United States for plant locations to produce synthetic liquid fuels, based on raw materials, water sources, and local interest.

This partially annotated bibliography contains references on boiling heat transfer of liquid metals. Emphasis is place on boiling heat transfer of liquid sodium, liquid potassium, and liquid rubidium. The period covered is 1950 to date. References are arranged alphabetically by title. Sources used in compiling this bibliography are: Abstracts of Classified Reports, Nuclear Science Abstracts.

The distribution of thermal neutrons in a W slug having a one centimeter aluminum end cap has been calculated on the basis of simple diffusion theory. It is found that the average neutron density, and therefore the power output, at the end of the slug is about 34% higher than the density far from the end cap. This result agrees well with the recent Argonne pile experiments (CP-1729).

The following report was undertaken to overcome poisoning difficulties that are caused by passage of solutions containing nickel through the Jones reductor/zinc amalgam reductors.

The following report examines primarily water and air factors that affect the quality of vacuum induction-melted uranium, yet follows experiments with other factors such as graphite and zirconium crucibles under dry and wet conditions, usage of hydrogen, oxygen, CO and other subject admitted to determine pressure-time relationships and residual gas compositions, as well as a study of water-gas reaction within the furnace.

The following report examines primarily water and air factors that affect the quality of vacuum induction-melted uranium, yet follows experiments with other factors such as graphite and zirconium crucibles under dry and wet conditions, usage of hydrogen, oxygen, CO and other subject admitted to determine pressure-time relationships and residual gas compositions, as well as a study of water-gas reaction within the furnace.

Summary: "Six different types of solutions of various concentrations were used to deoxidize uranium chips on a laboratory scale. None of the solutions tested appears to be more desirable than 50% nitric acid for deoxidizing uranium chip on a production scale."

The following report describes a countercurrent extraction column, which employs timed solenoid valves and pressurized feeds to provide a pulsing action to disperse the phases. This report further describes the 4-stage cycle of the column operation.

Work was completed on the high-temperature, high efficiency air filter. Technical assistance was given at a large-scale, privately financed run of an all-glass medium. Full-size filers have been produced in quantity and are offered by manufacturers; it is considered that commercial manufacture has been established. A survey was made of air sampling practices at 37 laboratories. Analysis of the survey results indicated that 22 different kinds of air-sampling filer media were in use among the laboratories questioned. We have recommended that air-assay practice be simplified by use of fewer media. A group of five media has been proposed as adequate for meeting all requirements. Laboratory work was done on the development of a high-efficiency, low-ash, all-purpose, air-assay paper. Two methods of approach were tried. In one an effort was made to produce cellulose fibrils in sufficient quantity and quality to act as the fine-fiber component of a filter. Only moderate success was attained. Better promise was shown by combining synthetic organic microfibers with cellulose fibers in a wet-formed sheet. No plant work was undertaken on this item.

The following report contains two parts on the analysis of astatine, neptunium and plutonium. Part A discusses a bent crystal focusing X-ray spectrometer that has been designed and built for the observation of the X-and gamma-rays emitted in association with radioactive decay. The instrument uses proportional counter detection and is described, as well as associated electronic circuits. The plutonium L X-rays from Cm-242 and the neptunium L X-rays from Am-241 have been measures. Values of the energies and abundances are reported. Then in Part B, it discusses some isotopes of astatine hitherto unreported that have been observed in bombardments of bismuth on the University of California 184" cyclotron.

Abstract: "The results of this investigation that it is necessary to remove fluoride prior to precipitation zirconium with mandelic acid or phenyl arsonic acid. Fluoride, however, has little effect on the cupferron method of precipitation. The discovery that zirconium fluoride is soluble in a mixture of aqua regia and sulfuric acid made it possible to dissolve the material without the addition of fluoride from hydrofluoric acid."

Abstract: "Some embrittling effects noted in Zr have been explained by the presence of hydrogen. This phenomenon was initially correlated with the existence of a second phase in the microstructure. The amount of this phase is reduced by vacuum annealing and shows a direct correlation with the hydrogen content of the specimen. X-ray and electron-diffraction evidence identifies the phase as ZrH. Observations are given on the solubilities, diffusion rates and equilibrium pressures of hydrogen in zirconium, and the application of these data to the removal of hydrogen."

The following report describes x-ray diffraction patterns of various compounds of americium and its crystal structures.

Abstract: "Type 347 stainless steel was selected for SIR applications requiring resistance to corrosion in sodium on the basis of limited corrosion data and extrapolation of experience in aqueous media. Subsequent testing indicated that carbide stabilization was not necessary for good resistance to corrosion in sodium. Evaluation of the unstabilized grade of 18-8 stainless steel, Type 304, was intensified because it offered a number advantages over Type 347. Type 304 was more readily available, required fewer strategic materials, was less expensive, and was reported to be weldable with less difficulty. From the results of this investigation, it appears that Type 304 can be substituted for 347 for all SIR applications where the slightly higher elevated temperature strength of 347 is not required."