Abstract: "Blacosolv, trichloroethylene, is used in degreasing uranium metal. Tests were made under possible industrial conditions to determine whether a hazardous reaction between uranium and Blacosolv could occur. Temperature-rise measurements showed that there was no reaction of the metal, in various states of subdivision, with Blacosolv at temperatures up to 850 F. However, a reaction was observed in tests under which the finely divided metal, wet with solvent, was subjected to a severe impact."

From abstract: "The composition of vapors from aqueous nitric acid solutions boiling at 200 mm mercury total pressure is established for solutions containing between - and 67.5 w/o nitric acid. The volatility characteristics of low concentrations of chloride in the same concentration range of nitric acid have been measured in solutions boiling at 200 mm mercury. The effects of chloride concentration and pressure of boiling are evaluated. A spectrophotometric method of the determination of chloride in nitric acid solutions is described."

Report discussing reaction of hydrogen with uranium in a range of temperatures and pressures. Experimental materials, methods and results are included.

From introduction: "Centrifugal casting appeared to be the only method by which the intricate shape could be produced in a cold mold. With this in mind, a program was initiated for the purpose of determining the feasibility of centrifugally casting plates of uranium-5 w.o chromium and uranium-2 w/o zirconium."

The following report discusses the development of methods for sealing the ends of metallic-cored fuel rods.

Report presenting a study that evaluates various types of refractories for use in a refractory-lined vessel that would be used for continuous reduction of uranium tetrafluoride to uranium metal.

Abstract: "The effects of nitrogen, slag, and hydrogen additions on the surface quality of rolled uranium rod were studied. The addition of 400 ppm of nitrogen resulted in severe striations. Slag inclusions elongated during rolling and produced short open seams in the etched surface. The effects of 9 to 10 ppm of hydrogen were obscured by defects in the original costings. These defects were caused by oxide films entrapped in the ingot."

This report follows investigations of methods for sealing the ends of stainless steel-uranium oxide fuel pins with the objective to develop an end-capping method that would give consistently good-quality closures in production.

Abstract: "The heat-treatment behavior of zirconium alloys containing 7 to 70 w/o uranium is described. The effect of oxygen contamination on the structure and hardness of these alloys is outlined. It is shown that in the initial stages pf transformation of beta zirconium-uranium solid solution into the low-temperature phases a potent hardening reaction occurs in alloys containing 20 to 70 w/o uranium. In this reaction the hardness may rise from 200 DPH characteristic of retained beta to values in excess of 400 DPH. Practical heat treatments have been developed which produce relatively soft alloys. The microstructures and hardnesses produces by these treatments are shown."

This report discusses studies revealing the tensile properties, hot hardness, and heat treatment characteristics of uranium alloys with added aluminum or zirconium.

This report studies ammonium dichromate and the conditions it needs to be under in order to precipitate and be isolated from an aqueous system.

This report discusses a study regarding the properties of uranium with added chromium, silicon, or titanium. This study was conducted in order to evaluate the effects of alloying on the mechanical properties of base metal.

From abstract: "The internal friction of recrystallized uranium has been shown to depend directly on heating and cooling rates and on the rate of application or removal of an external stress during measurement. At zero heating or stress rate, the internal friction falls to a low value and appears to decrease indefinitely at room temperature. Micrographs showing twin disappearance on removal or reversal of load are shown...It is concluded that the various internal-friction phenomena are the result of the stress-induced motion of twin boundaries." Results are compared with similar studies as well.

Abstract: "A method for determination of dibutyl phosphate in solvent streams containing tributyl phosphate is outlined. The method is based on analysis for total uranium of total phosphate after removal of uranium and phosphate in excess of that present as uranyl dibutyl phosphate. Results on plant solvent samples are presented. Difficulties with precipitation of [...] dibutyl phosphate, when fresh solvents were employed, are discussed. Small amounts of nonphosphate uranium-complexing agents were found in plant solvents. Diluent degradation is postulated as the source of these components. Emulsion-formation tendencies appeared to correlate better with concentrations of these contaminants than with dibutyl phosphate content."

Abstract: "The corrosion rate in 680 F water of the uranium-50 w/o zirconium binary alloy was found to be -0.20 mg/(cm2)(hr), and that of the uranium-40 w/o zirconium binary alloy was -0.34 mg/(cm2)(hr). Both alloys correlated uniformly, with no evidence of discontinuous failure. Normal variations in interstitial content in either alloy had no significant effect on corrosion behavior. Tantalum additions, in the range of 0.2 to 5 w/o, improved the corrosion rate of the uranium-50 w/o zirconium base, with a minimum rate of -0.06 mg/(cm2)(hr) for the 5 w/o tantalum alloy. The 5 w/o tantalum addition to the uranium-40 w/o zirconium alloy. The 5 w/o tantalum addition to the uranium-40 w/o zirconium alloy decreased the corrosion rate of the base to -0.11 mg/(cm2)(hr) in the [...] condition only. In either conditions, the 5 w/o tantalum alloy failed discontinuously. All other additions to both bases either had no effect or decreased corrosion resistance. These included aluminum, chromium, iron, molybdenum, nickel, platinum, tin, titanium, tungsten, and vanadium additions."

Report discussing studies regarding properties of the zirconium-uranium epsilon phase related to stability and existence range. Data showing this phase's thermodynamic stability is presented as well as the zirconium-uranium constitutional diagram. Oxygen and nitrogen effects on zirconium-uranium alloys and epsilon-phase alloys is included as well as ternary zirconium-uranium-oxygen diagrams.

Abstract: "Approximate melting points have been determined for five samples of uranium tetrafluoride representing incompletely converted uranium dioxide and covering the range from about 2 to 20 w/o UO2, using the method of differential thermal analysis. The results indicate the melting temperatures are in the range of 920 to 980 C. No significant correlation between melting point and UO2 content was observed, possibly because of calcite formation. Similar results were obtained on synthetic mistakes of UF4 containing from 10 to 40 w/o UO2."

This report discusses mechanical properties and heat treatment of some uranium-titanium alloys. These alloys were tested for use as fuel-element material.

The following report focuses on research made to determine whether the service performance of UO₂ fuel-elements cores for the PWR can be improved by certain ceramic or metal additions.

This report is one of a series of five, dealing with alloys of the uranium-zirconium series. Particularly, this report focuses on the corrosion properties of uranium alloys, with zirconium as the major alloying agent, in high-temperature water.

From abstract: "The inert-gas metal-arc welding process was used to determine weldability studies of various aluminum alloys that are being considered for use as can materials. The solid-phase and induction welding processes were also investigated for making can closures."

Report describing a study of fabricating conditions for bonding zirconium and uranium alloys by roll cladding.

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.

A report which covers an investigation of techniques for producing hot-dip Al-Si coatings on uranium sheet. Also, the study is concerned with the effects of time and temperature of dipping on the intermetallic zone and its ductility.