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 following report follows the inspections of a number of eddy-current instrument procedures. The objectives of these tests were to detect both weld defects and lack of integrity of the body of the fuel elements.

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The following report proposes various methods in injecting and heating in mirror machines, using high-energy ion beams.

From introduction comments: The present analysis is intended to examine the relations for "adiabatic" injection in general from a different point of view.

Letter opinion issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, John Ben Shepperd, regarding a legal question submitted for clarification; Constitutionality and effect of Senate Bill 97, the Probate Code.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, John Ben Shepperd, regarding a legal question submitted for clarification: Availability of the Federal Social Security program to school districts.

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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 …

This report discusses the corrosion of fuel element jackets and process tubes. A brief background in electrochemistry is presented, and the corrosion of aluminium, aluminium alloys and zirconium is summarized.

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It has been determined that the use of a poor quality uranium for cores was responsible for non-reproducibility in several series of corrosion samples. A better quality core material will be used for future studies of the effects of outgassing on the corrosion resistance of nickel-plated uranium. Tools for extrusion cladding experiments at BMI are expected to be ready for use in early August. Five nickel-plated steel tubes were internally clad with aluminum by {open_quotes}hot drawing.{close_quotes} Although diffusion zones were formed, the weak bond was parted on cooling due to the differences in the thermal expansion of aluminum and steel. Varying degrees and patterns of segregation have been found in uranium-aluminum castings which were cooled through the liquids-solidus region at different rates. Equipment changes will be made to provide a wider range of cooling rates.

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Report on methods for making spherical uranium particles.

Diffusion in an arc plasma across a magnetic field is investigated. The geometry is similar to that reported in ORNL-1890 but with the addition of magnetic mirrors on the ends of the arc chamber. It is shown that mirrors do not eliminate the "short circuit" effect. Comparison of the e-folding length, rₒ, of the radial ion density with and without mirrors, affords a direct measurement of ℓ/λ where ℓ is the arc length and λ the mean-free-path. In addition rₒ is independent of gas pressure with mirrors and varies as √p without mirrors. The condition for the elimination of the "short circuit" effect is discussed, as well as the case in which the "short circuit" is still present but the ions diffuse (rather than stream) to the end walls. In this case rₒ is directly proportional to the gas pressure. These effects are compared to some experimental results of Neidigh

A direct titrimetric method for the determination of trivalent uranium in uranium trifluoride and mixtures of fused fluoride salts was developed. The method is based on the stoichiometric oxidation of trivalent uranium to the tetravalent oxidation state with an acidic solution of methylene blue. The sample containing trivalent uranium is dissolved at room temperature in an excess of standard methylene blue solution in a carbon dioxide atmosphere; the excess oxidant is variation of the method is 1.5 per cent for 5 mg quantities of trivalent uranium. The method was applied to various mixtures of fluoride salts containing both trivalent and tetravalent uranium.

An anion exchange precipitation procedure was developed for the determination of Cs¹³⁷ in various aged fission product waste solutions, and other solutions containing Cs¹³⁷. The procedure is based on the ability of an anion exchange column to function simultaneously at an anion exchanger and as a precipitating agent (1).