From introduction: This work is a survey of possible uses of ceramic materials in Hanford-type fuel elements.

Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."

Report discussing the progress of research projects at Battelle Memorial Institute relating to civilian applications during August 1956.

This report follows a preliminary study on uranium migration in pressed and sintered UO2-bearing bodies based on MoSi2 or Al2O3.

Abstract: "Differential thermal-expansion effects in brazed joints involving Type 310 stainless steel and GE-62 brazing alloy were investigated. The work included dilation and modulus-of-elasticity measurements using homogenous cast specimens and observations on bimetallic cantilevers made of the two constituents. No anomalies were found, although there were irregularities in the expansion of the brazing alloy which were ascribed to a solubility phenomenon. The elastic modulus of the brazing alloy was determined. Cantilever deflections with temperature and with load were measured, and the results were interpreted using equations which treat the specimens as true bimetals consisting of two homogeneous components. The difference in thermal-expansion coefficients obtained in this way from the temperature-deflection data was consistent with the dilation measurements. The load measurements yielded an average elastic modulus for the bimetal which was about two-thirds of what would have been expected from knowledge of the components. This discrepancy probably arose from porosity which was observed in the braze components."

Technical report surveying radio-chemical analyses by ORNL's Analytical Chemistry Division and Health-Physics Division of large volumes of rainwater for plutonium, uranium, and fission products. Overall, carrying efficiencies for Al(OH)3 scavenging of rainwater were determined for these elements, as well as for Pu and U. [From Abstract, Introduction]

Report that discusses the possibility of testing the T-invariance in μ-meson decay. The author describes a past experiment performed by Lee and Yang, as well as the specifics of the proposed experiment to test the time reversal in μ-meson decay.

Report discussing details of the design for the Bevatron at the University of California Radiation Laboratory. The Bevatron is a "6-billion-electron-volt (Bev) proton synchotron. This device will receive a 10-million-electron-volt (Mev) proton beam from a linear accelerator, and further accelerate a reasonable percentage of these protons, at a nominally constant radius of 600 inches, to a final energy greater than 6 Bev."

Abstract: "The quantities of interest in a confined plasma include the electric and magnetic fields, current density, diffusion velocity, temperature, pressure, and particle density. Equations governing the distribution of these seven variables are given in this report and special cases of a one-dimensional steady-state plasma are examined in detail. The solutions are given in graphical form."

Abstract: "A cylindrical coil has been designed for pulsed field operation suitable for use in a model thermonuclear reactor. The coil has an eight-inch inside diameter and a length of fifty-one inches. Magnetic mirrors at the ends consist of double-layer solenoids six and one-half inches long designed to slip over the main coil. Subsequent models of this coil have been fabricated which improved the electrical insulation provided by the bonding materials and the mechanical rigidity of the coil. Peak central fields of fifteen kilogauss and mirror fields of thirty kilogauss have been obtained."

Report containing results of a study regarding concentration of radioiodine in edible plants fed to animals.

Abstract: "A titrimetric method for the determination of fluoride in plutonium is reported. Prior to a steam distillation of the fluoride, the bulk of the plutonium is separated by precipitation of the sulfate. The fluoride in the distillate is titrated at a pH of 3.2 with 0.001 M thorium nitrate, using chrome azurol-S indicator. Applied to samples containing 1 to 15 parts per million fluoride, the recovery is 87% and the precision on the 95% confidence level is +/- 0.65 ppm."

Various figures depicting views and components of a device for coating the "Model 100" 8-faced metallic rotating mirror with an equal amount of material on each mirror face.

Report describing the proceedings of the second symposium on the application of pulsed neutron source techniques.

Report discussing both the probability of having a reactor accident that would release fission products, as well as the probable extent of the release of the products. This information, along with the contents of the fission products themselves, are based on statistical analysis and educated guesses.

"The e-folding time for the free-molecule pump-out time of the vacuum tank used for the β⁺ ray experiment (N¹⁹ at 20°C) is found to be of the order of 46 millisec, and that used for the Felix experiment (D₂ at 20°C) of the order of 12 millisec. In the Felix tank a particle bounces off of the walls on the average about 30 times before escaping, hence a "getter" material coated on the walls of the tube should result in a slightly more rapid pump-out time."

Introduction: "A corrosion test program, to determine the suitability of LaBour B-55 and Worthite for use in the construction of circulating pumps for th UO3 process has been completed and the data are appended."

The Redox solvent extraction process for the separation of uranium and plutonium from their fission products and from each other has operated on an over-all basis very successfully for more than four and one-half years. During this time, there have been occasional periods of high product losses and/or poor separation of fission products from uranium or plutonium as well as periods of poor operability due, among other things, to emulsification and entrainment. The search for the cause of these various process troubles has resulted in almost continuous testing of the process solvent in attempting to determine its contribution, if any, to these difficulties. This report documents the history of the Redox Plant solvent.

This memorandum summarizes the results of an analysis to determine the extent of displacement of the EOCR core due to blowdown in case of several postulated hot main gas coolant pipe failures. Results show that the core will be damaged for any hot pipe double-ended failure. Excepting the improbable case of no coolant flow existing proper to the break, the core will be damaged for any hot pipe fracture exposing a total flow area to the atmosphere equal to that of one pipe. Smaller breaks will probably be safe in this respect.

Report discussing the results of Project "A," which had three main components: "Effect of P2O3 Concentration on the Distribution Coefficient for Uranium Between Crude Phosphoric Acid and O.P.P.A.," "Effect of Chloride Concentration in Phosphoric Acid on the Distribution Coefficient for Uranium Between O.P.P.A. and Phosphoric Acid," and "The Use of Di-Isobutyl Carbinol in the Preparation of a Solvent to Extract Uranium from Phosphoric Acid (N.P.P.A.)."

This report covers an investigation meant to find the feasibility of producing corrosion resistant zirconium from sponge by special melting techniques. The zirconium metal has certain required specifications, such as: the metal must be free from bafnium, and it must be free from other impurities of undesirable neutron cross section.

"This memorandum is a survey of the properties of [U-Bi] reactors for U235 as a fuel and U233 as a fuel using a larger density for the graphite [for calculations]. This will include properties of the core and various reflectors which will be useful for large machine calculations of reflector savings, fast and thermal fluxes, and quantities of interest based on two-group calculations."

Report discussing statistical quality control for the period of December, 1951-February, 1952. Statistical quality control is provided for studies of the General Ionic Analyses Laboratory, the HR Control Laboratory, and the X-10 Laboratories.

Introduction: "Since it has been found that zirconium and zirconium-tin alloys may be embrittled by certain heat treatments, it was decided to determine if welding of these materials affects their ductility in any way. A single bend test in both the longitudinal and transverse directions was used for evaluation of the variables considered."