Abstract: "The Institute for Environmental Studies at Louisiana State University conducted research into the potential use of Louisiana salt domes for disposal of nuclear waste material. Topical reports generated in the 1981 and 1982 related to Vacherie and Rayburn's domes are compiled and presented, which address palynological studies, tiltmeter monitoring, precise releveling, saline springs, and surface hydrology. The latter two are basically a compilation of references related o these topics."

This report follows critical-assembly studies made to provide engineering and physics data to aid in developing the Gas Cooled Reactor Experiments.

Report discussing a study to obtain a quantitative measurement of the movement and distribution of hydrogen among components such as magnesium metal chips, uranium tetrafluoride, and magnesium fluoride slag, similar to what would occur during a reaction in a thermite bomb.

From introduction: "The work described here was part of an integrated investigation of the fundamental properties of uranium oxides done for the Mallinckrodt Chemical Works. Electrical measurements were employed to characterize the oxides produced by various processes from different starting materials. The basic objective of the program was to determine those factors which affect the sintering characteristics of uranium dioxide."

Report discussing the survey work done at the Battelle Memorial Institute with the objective to successfully build a gas-cooled reactor.

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

This report follows work performed to determine the effects of large boron additions on the fabricability and room-temperature tensile properties of various steels for reactor shielding.

This report covers a study of the deformation characteristics of uranium in grooved rolls. The study's purpose was to provide a basis for possible improvements in the uniformity of the rolled rod produced for the Hanford and Savannah River reactors.

The creep strength and tensile properties-were determined in vacuum for beta-quenched, derby uranium. The stresses to produce a secondary creep rate of- 0.0001 per cent per hr at 100, 250, 400, and 500 deg C were 48,000, sile strengths were 114,500, 35,100, 11,100, and 8,500 psi at temperatares of 28, 300, 500, and 700 deg C, respectively. The creep and tensile strengths decrease quite rapidly with increasing temperature in the temperatare range 250 to 400 deg C.

This report of the Battelle Memorial Institute covers information on development regarding various materials.

From introduction: "This report presents the results of an experimental program to evaluate engineering problems which might be encountered when circulating NaOH-UO3 slurry through a thermal cycle."

From introduction: "This report summarizes the work done on a study of fused-salt systems in a search for new liquid fuels suitable for use in a nuclear power reactor."

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

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."

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

Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."

Abstract: "The mechanical properties of a large number of zirconium alloys have been investigated. These alloys include zirconium-tin and zirconium-tin-uranium. Tensile tests have been run on these alloys at room temperature, 500 F, and 600 F. Hot-hardness data have been obtained from room temperature to 1600 F, with particular emphasis on the hot-rolling range. Creep tests and fatigue tests have been run on a number of zirconium-tin alloys at 500 F."

Abstract: "Creep and creep-rupture tests were made on 25-O aluminum sheet at temperatures of 500 and 550 C. The estimated stresses that will produce 0.5 per cent deformation and rupture in 10,000 hours at 400, 450, 500, and 550 C (data at 400 and 450 C are from BMI-T-29, dated June 9, 1950) are presented."

From abstract: "Results are presented which suggest the possibility of satisfactorily extracting uranium from pitchblende feeds with neutral ether, without the necessity of removing sulfate, by the addition of a sufficient quantity of iron to the feed." Other factors' effects on extraction were tested and arsenic was traced throughout extraction.

The following progress report was compiled by the research and development division of the zirconium pilot plant. This report discusses two iodination and deposition runs that were completed as of August 20, 1951, as well as the third iodination run that uses a vaporizer condenser that condenses approximately 40 pounds of zirconium iodide.

From abstract: "The effects of solution concentration and acidity on extraction of uranium by diethyl ether have been investigated... The approximate solubility of vanadium pentoxide in nitric acid was determined."

Abstract: "Costs have been estimated for the production of uranium and pure thorium from monasite concentrates by a process involving (1) reaction of monasite with caustic soda, (2) dissolution of the hydrous oxides in hydrochloric acid, (3) separation from the bulk of the rare earths by hydroxide precipitation of thorium and uranium, and (4) purification by solvent extraction."

Report describing a method for recovery of high yields of thorium and uranium from monazite sand concentrates. Monazite is decomposed into hydrous metal oxides, which are dissolved in an acid. The solution is then separated into a precipitate, which seperates from thorium and uranium. An alternate separation method is evaluated.

From abstract: "Details are presented on the processing of monazite sand and on separating the rare earths from thorium and uranium. Solvent-extraction and ion-exchange techniques for purifying thorium and uranium are described."