Results of experimental investigation for improving intensification and to reduce stress concentrations for anvil redesign.

Investigation conducted to determine the cause of cracking, during tension, on the surface of tensile specimens of uranium-molybdenum alloys.

Early results from actual laboratory operation of a more versatile magnet supply.

The purpose of this study was to provide a means for evaluating the various parameters involved in the design and performance of levitation coils.

Report on the determination of several physical properties, pertinent to uranium extraction, for a number of ethers and related compounds.

A method of mathematically fitting a curve through a given ordered set of points has been developed and programmed in fortran computer language.

Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division.

Special welding techniques for joining Inconel weld overlays on type 316 stainless steel tubesheets and channels are described. The program for the development of the required welding procedures are divided into three specific programs: overlaying Inconel filler Metal 82 on type 316 stainless steel, welding type 316 stainless steel tubes to a type 316 stainless steel tubesheet, and welding Inconel-type 316 stainless steel composite tubes to Inconel weld overlaid type 316 tubesheets. Shock tests are described which attempt to assimilate the most drastic thermal transient that could occur in both units and to evaluate the effect of the resulting stresses on the Inconel overlay and the tube-to-tubesheet welds. (N.W.R.)

From introduction: "Irradiation experiment performed to simulate burnup data under close to reactor temperatures."

From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."

From summary: "The report contains descriptions and discussions on nuclear safety testing."

From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."

Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.

Quarterly progress report metallurgy research operation at Hanford Atomic Products Operation in Richland, Washington.

Analysis of the stability of boiling water reactors.

From introduction: "Evaluations to determine cause of fuel rods breakage following irradiation."

From abstract: "The experimental determination of the effects of sodium ingress on high-performance oxide fuels is described. Capsule design, fabrication, irradiation, examination, and analysis are described in detail."

From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.

From introduction: "The purpose of this report is to describe the observations made during the post-irradiation examination of HPD-2S, and to discuss possible modes of failure.

Report comparing the fuel cycle costs and temperature coefficients of reactivity for PuO2-UO2 fuel in multiple megawatt reactors.

Report evaluating the design characteristics and limitations of fixed blankets for breeder reactors. This also includes economic considerations for each tested blanket.

Report describing a study that "was undertaken to provide a sound basis both for the optimization of either axial-flow or cross flow steam generators and for the evaluation of the relative merits of major design features" (p. 2).

Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.

Report describing the results of laboratory tests with procedures for calibration of equipment and performance requirements.