Abstract: Information on five uranium binary alloy systems has been surveyed. These systems are the alloys of uranium with zirconium, chromium, columbium, vanadium, and molybdenum. The equilibrium diagrams are discussed, and where available, data have been included on diffusion studies, cladding experiments, and mechanical properties.

The bibliography provided investigates the following sources: Chemical Abstracts 1947-1950., Metallurgical Abstracts Vols. 1-18., ASM Review of Metals Literature Vols. 1-6., J. Institute of Metals Vols. 78-80 (No. 7)., Physics Abstracts 1937-1950.

From summary: "The relative absorptions of X-rays by various substances are listed as a guide to the application of the X-ray photometric method in chemical analysis and to the estimation of interference by extraneous substances."

This report follows an investigation of a cargo truck found contaminated by various radioactive material on a routine trip from Arco, Idaho to the Hanford plant on May 8, 1952. The report analyzes the truck's route in an attempt to find the location of the contaminating region.

A buncher and pre-accelerator for A-12 is described that has 360 degree acceptance and could handle a current of one ampere from a low voltage source.

Most of the publications in the open literature available to us agree that sodium does not readily react with graphite, though potassium, rubidium, and cesium readily enter between the planes of the graphite lattice. In view of the conflicting evidence available, it seems inadvisable without very extensive further study to consider the use of graphite in direct contact with liquid sodium, except under very mild conditions of temperature and irradiation, and then only with very pure sodium and completely graphitized graphite.

Abstract: An attempt is made to correlate the thermal neutron fission cross sections of various nuclides. An empirical relationship is observed when the logs of the ratios [thermal neutron fission cross section of (Z,A)/thermal neutron capture cross section of (Z,A)] for several nuclides are plotted against their neutron binding energies [binding energy of a neutron to (Z,A)]. The log of the σf/σc ratio decreases markedly with decreasing neutron binding energy."

Report discussing tests of the fissionability and capture cross-section of produced U²³².

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."

This document describes a method in determining solid solubilities using strain-aging techniques, explaining a non-uniform yielding of the alloy in question.

Thesis discussing the examination of radiation spectra emitted in the decay of various nuclides using a 10-inch bent-crystal spectrometer. For the most part, the radiations observed were x-rays and very soft gamma rays.

From abstract: "The energies of fragments from fission of U-235, U-238, and Pu-239 by 14-Mev neutrons, from fission of U-238 and Pu-239 by thermal neutrons have been measured in a Frisch grid ionization chamber."

From summary: "In order to estimate the effect of placing bismuth and thorium layers near the MTR core, radial flux distributions and k[infinity] values were calculated for cylindrical reactors having cylindrical layers of these materials of the same height as the core and beryllium reflector and placed either next to the core or embedded in the beryllium reflector."

This report discusses what effects the shift of an orbital axis relative to the center of the table-top stellarator tube as well as the magnitude of these effects.

Abstract: "Two cases are considered. In Case I, the reactor water velocity is optimized to obtain a minimum annual cost (including amortization and operating costs) for the cooling system along. The optimum velocity for a 310 megawatt reactor is calculated to be ~25 feet per second, compared to the present design value of 30 feet per second. In Case II, the velocity which will give the minimum cost of product under the assumptions of varying power and production rate is found to be in the range from ~25 to ~40 feet per second, depending on the assumptions with respect to the variation of total investment in the reactor complex with design production capacity."

Introduction: The experimental work at Mound Laboratory on bismuth casting and the sealing of aluminum irradiation containers is an outgrowth of the bismuth recovery project. Since the recovered bismuth contains residual activity it is necessary that the bismuth be processed to the point that no contamination will result from shipment or any subsequent operations required to prepare the bismuth for irradiation. In order to satisfy these requirements the work here has consisted of investigating methods of preparing the bismuth slugs in the shapes required and of mechanically sealing the aluminum container.

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."

This report describes how to achieve the variation in maximum power density and maximum heat flux of the core and blanket thorium plates in the converter reactor with irradiation time.

This report describes the construction of a reactor and the research conducted in the reactor such as solid fuel and liquid fuel research, boiling reactor experiments, CP-6 bond testing program, and water quality control experiments for CP-6 program.

Early in the design of the Mark I accelerator it was decided to install magnetic lenses in the drift tubes. A number of model magnets were constructed and tested to determine the best design for these lenses. This report includes only the results of the tests on the final models of the magnets that are designed for Mark I.

Isotopes of americium and curium with mass numbers less than 242 have been produced by cyclotron bombardment techniques, and several of their nuclear properties have been investigated. The partial alpha half-lives of Am(239), Cm(241), and Cm(240) and the partial half-life for spontaneous fission of Cm(240) were measured. The alpha decay daughter of Cm(238) was found and evidence for the discovery of Am(237) (an -1 hour electron capture activity) and Cm(239) (an -10 hour electron capture activity) has been presented. An Appendix indicating the conditions for separation of the plus three actinides by selective elution from ion exchange resin with citric acid has been included.

The free streaming of neutrons in a cylindrical cavity is investigated. Using experimental data for the flux distribution along the walls, the direct beam hole loss and leakage into the target from the lattice is estimated for the MTA system.

Quarterly summary report of studies conducted through the University of California Radiation Laboratory. Some results reported in the report may be of a preliminary or incomplete nature.

In the past it was felt that the easiest way to treat a three group equation for a MTA lattice was to solve it without certain terms. This iterative procedure converged rapidly for a medium with depleted uranium fuel, and in fact, a second iteration was not needed.