This study is a part of the U.S. Department of Energy's (DOE) Civilian Radioactive Waste Management (CRWM) Program and discusses the geologic investigations made on the salt beds of the Paradox Formation.

Abstract: "A geologic reconnaissance map was prepared of the supradomal area of Keechi Dome, Texas, at a scale of 1:24,000. To do this, available data were compiled, and field checking and new mapping were done where access was permitted."

Abstract: "An updated geologic reconnaissance map was prepared of the vicinity of Cypress Creek Dome, Mississippi, at a scale of 1:24,000. Compilaion of previous work, field mapping, and heavy material analyses were used to prepare the map."

Abstract: "A geologic reconnaissance map was prepared of the supradomal area of Richton Dome, Mississippi, on a scale of 1:24,000. To do this, previous work was compiled and consolidated, and field mapping and heavy mineral analyses took place."

Abstract: "A geologic reconnaissance map was prepared in the area of Vacherie Dome at a scale of 1:24,000. To do this, the available data were compiled, resistivity surveys were conducted, and reconnaissance field mapping took place. Then all the information was consolidated for the map preparation."

The following report summarizes the conclusions and what's been done on the work on the Quaternary geological studies of Rayburn's Salt Dome, North Louisiana Salt Dome Basin.

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."

Summary: "The potential impacts to visual resources, resulting from construction and operation of a nuclear waste repository and transportation route in the Gibson Dome Area of southeastern Utah, were evaluated."

From abstract: "This report provides a comprehensive summary of the [guarded straddle packer] system development."

The following report provides a compilation of appendices focused on the geological investigations of Vacherie salt dome in the north Louisiana Salt Dome Basin.

From introduction: "The following report documents the a preliminary evaluation of the geologic, geotechnical, and hydrologic conditions for the overburden materials above Richton Dome."

The following report summarizes the conclusions and what's been done on the work on the Quaternary geological studies on the Vacherie Salt Dome, North Louisiana Salt Dome Basin.

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."

Introduction: "The tensile properties, hot hardness, impact strength; and corrosion resistance of some arc-melted, iodide zirconium alloys have been determined. The alloys investigated include binary alloys of zirconium containing zero to five per cent tin, binary alloys of zirconium containing zero to 0.14 per cent nitrogen, and ternary alloys of zirconium containing tin and nitrogen, tin and uranium, and uranium and beryllium."

This report explores the production of beta silicon carbide, a low-temperature, cubic modification of cubic silicon carbide. The temperature, heating time, type of starting material, and proportion of starting materials were all varied in order to test yields of beta silicon carbide.

Abstract: "As a possible aid in the selection of ceramic materials for use in the fabrication of high-temperature reactor elements, the reported properties of 23 refractory oxidation-resistance ceramic compounds are tabulated. The thermal stresses and heat throughout capacities for nine of these compounds are estimated for conditions of steady heat flow and uniform heat generation in the temperature range of 1500 to 2500 F. The compounds studied have macroscopic thermal-neutron-absorption cross sections lower than 0.2 per centimeter. Data concerning the high-temperature stability of uranium compounds are tabulated for those with melting points above 2450 F."

Abstract: "The mechanical properties and corrosion resistance of induction-melted, zirconium-tin alloys have been determined. The alloys investigated contained from zero to five per cent tin and up to 0.3% carbon. The zirconium used was United States Bureau of Mines sponge zirconium. The mechanical properties investigated include the tensile, hot-hardness, and impact properties."

The following report discusses the method of rolling uranium rods and strips under various rolling conditions and the roll-separating force measured.

Abstract: "The protection of thorium in hot water was studied. Copper electrocladding on thorium offers promising protection against hot water. The corrosion of thorium in 95 C water was reduced appreciably by a thorium phosphate film. The results of this abbreviated investigation offer a basis for the development of a method of protecting thorium at elevated temperatures in corrosive media."

Abstract: "Thorium tubes were cold drawn from extruded tube stock and also from drilled hot-rolled rod. Total reductions up to approximately 85 per cent were accomplished by conventional tube-drawing methods, without an intermediate anneal. The hard-drawn tubes had high tensile strength, but the ductility, as indicated by flaring and flattening tests, was low."

Report discussing studies on various types of protective coatings for a molybdenum sheet. Procedures, materials, and results of each coating are included.

Abstract:"The creep resistance of various uranium binary alloys was investigated at 1500 and 1800 F in vacuum. Tests were made on alloys of uranium with beryllium, columbium, molybdenum, tantalum, titanium, and zirconium and on molybdenum-UO2 composites. Of the alloys examined, those of the uranium-molybdenum system exhibited the best creep resistance. At 1500 F, creep rates of about 0.005%/hr were produced in uranium-molybdenum alloys by a stress of 2500 psi and, at 1800 F, similar creep rates were obtained in composites of 90 wt % molybdenum-10 wt % UO2 by a stress of 12,000 psi."

Abstract: "The solubility of oxygen in uranyl sulphate solutions and in water at 212, 275, and 325 F, and at oxygen partial pressures up to 1500 psia was investigated. The results are presented in tabular and graphic form. The solubility is proportional to the partial pressure of oxygen. The ratio of solubility in the uranyl sulphate solution to solubility in water at the same temperature and pressure is a function of the concentration of the salt in solution."