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- The Recovery of Uranium from Chattanooga Shales
- Recovery of uranium from Chattanooga shales.
- Hazards Summary Report for the Battelle Research Reactor
- From summary: "This report was prepared for the Advisory Committee on Reactor Safeguards for their review and consideration of the potential hazards concerning the Battelle Memorial Institute Research Reactor."
- Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin
- 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."
- Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin
- 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."
- Mechanical Properties of Iodide Zirconium Alloys
- 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."
- The Preparation of Beta Silicon Carbide
- 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.
- Evaluation of Oxidation-Resistant Ceramics for High-Temperature Reactor Elements
- 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."
- Mechanical Properties of Zirconium-Tin Alloys
- 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 Rolling of Uranium
- The following report discusses the method of rolling uranium rods and strips under various rolling conditions and the roll-separating force measured.
- Electroplates on Thorium
- 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."
- The Fabrication of Thorium Tubes
- 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."
- Protective Coatings for Molybdenum
- Report discussing studies on various types of protective coatings for a molybdenum sheet. Procedures, materials, and results of each coating are included.
- Creep Strength of Uranium Alloys at 1500 and 1800 F
- 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."
- The Solubility of Oxygen in Uranyl Sulphate Solutions at Elevated Temperatures
- 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."
- The Ductility of Brazed Stainless Steel Joints
- Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1800 F in air was found to triple the room-temperature ductility of the brazed joint."
- The Application of Ceramics to Hanford Fuel Elements
- From introduction: This work is a survey of possible uses of ceramic materials in Hanford-type fuel elements.
- The Properties of High-Uranium Alloys Containing Zirconium or Chromium
- From abstract: "Various physical and mechanical properties have been determined for high- and low-carbon base uranium, uranium-chromium, and uranium-zirconium alloys. These data complement those obtained at ANL on the same materials."
- Extrusion Cladding of Fuel Element
- 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."
- Aluminum Cladding Long Uranium Plates by Solid-State Bonding
- From introduction: This report covers an investigation of solid-state bonding as a technique for aluminum cladding uranium plates of 3 by 0.180-in. cross section in lengths up to 14 ft.
- Electrodeposition of Aluminum on Uranium
- Abstract: "Aluminum electroplating was studied in a search for new methods of cladding uranium fuel elements. Uranium electroclad with 12 mils of aluminum over a 0.5-mil (or nickel plus copper) electroplate resisted corrosion for more than 100 hr in boiling water. This quality of protection was effected by hot pressing the electroclad uranium with 5.1 tons per sq in. for 5 min at 950 F. The electroclad uranium with hot-pressed samples paralleled those of later experiments with hot-pressed wrought aluminum claddings on uranium. In both cases, the uranium was electroplated with thin (0.5 mil) layers of metals to prevent aluminum-uranium diffusion, to aid bonding, and to assist in corrosion protection. This aluminum electroplating study helped to define the importance of the intermediate coating between the aluminum and the uranium, the effect of good bonds between the various layers, and the effects of hot pressing in protecting uranium with an aluminum cladding."
- Electroplated Metals on Uranium for Aluminum Cladding
- Abstract: "Aluminum-clad nickel-plated uranium is corrosion resistant in boiling water. Samples with intentional defects in the aluminum-nickel clodding layers, after testing for more than 300 hr. showed no sign of rapid failure. The study of electroplated metals on uranium for aluminum cladding has defined the effects of several processing variables on the corrosion resistance. The quality of the uranium and the quality of the aluminum-nickel bond were important. Heat treatment and vacuum outgassing of the nickel-plated uranium prior to aluminum cladding were beneficial, and minimizing the amount of air present in the hot-press assembly was desirable. Variation in the steps for electroplating on uranium did not affect the corrosion resistance of aluminum-clad uranium."
- Apparatus for visual study of corrosion by hot water
- Report describing an apparatus for visual study of corrosion of uranium by hot water. A windowed autoclave was designed and constructed to permit visual study of the reaction under conditions simulating a cladding failure in service.
- Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Heat Treatment
- Introduction: "The uranium-5 w/o chromium alloy has been intensively investigated for use in a power reactor in the as-cast condition. However, when cast sample fuel elements were subjected to irradiation, their stability was found to be unsatisfactory. In order to improve the behavior of the alloy, a program of grain refinement by heat treatment was begun. The effect of chill casting on the heat-treated grain size was also investigated."
- Low-Melting Alloys for Cast Fuel Elements
- The following report follows an investigation made to determine the composition of uranium-rich ternary eutectic alloys most suitable for reactor application in the as-cast condition. These determinations were made based metallographic examination and thermal analysis of as-cast alloys.
- Ceramic Investigations of UOâ‚‚
- This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
- Annealing of crystal distortion in irradiated graphite
- From introduction: "As part of the program for improvement of graphite, the structural characteristics of graphite have been studied to determine the relation between physical and structural changes during irradiation."
- The Roll Cladding of Uranium With Aluminum
- Report discussing a study regarding rolling as a technique for making uranium fuel elements that are flat-plate and aluminum-clad.
- Topical report on anion-exchange studies on the separation and purification of uranium and thorium
- A report which describes the separation of uranium from thorium in carbonate, hydrochloric acid, and sulfuric acid solutions by anion-exchange resins.
- Final Report on Recovery of Thorium and Uranium From Monazite Sand : Volume 1
- 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.
- Final Report on Recovery of Thorium and Uranium From Monazite Sands, Volume 2
- 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."
- Estimated Manufacturing Costs for the Recovery of Thorium and Uranium from Monazite Sand
- 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."
- The solubility of sodium phosphate in sodium hydroxide solutions
- A report about how trisodium phosphate can be most satisfactorily removed from sodium hydroxide solutions at 40 percent sodium hydroxide concentration, or higher, the temperature being practically immaterial, or it can be removed antisfactorily from 15 to 30 per cont sodium hydroxide at 25°C
- Progress Report on Refining of MgX and Other Uranium-Bearing Materials
- From abstract: "Results of two methods of reducing the phosphate and vanadate contents of MgX, a uranium precipitate from the Belgian Congo, are described...Chemical analyses of several samples of pitchblende and MgX are presented."
- Progress Report on Refining of MgX and Other Uranium-Bearing Materials
- 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."
- Progress Report on Refining of MgX and Other Uranium-Bearing Materials
- Abstract: "The effects of acidity on extraction of vanadium and molybdenum by diethyl ether are described. Solubility data for several vanadium compounds in nitrate process solutions are presented. Preliminary results on the extraction of uranium from process slurries by tributyl phosphate are reported, including data on the contaminants extracted with the uranium."
- Progress Report on Refining of MgX and Other Uranium-Bearing Materials
- From abstract: "Results of tests investigating the effects of feed and scrub acidities on the extraction of uranium and contaminants from process slurries by tributyl phosphate-Gulfspray Naphtha in a Scheibel continuous extractor are described. Studies on the fractional precipitation of MgX from a dilute sulfuric acid system throw considerable light on the probable constitution of MgX. Further data on the effect of acidity on the extraction of molybdenum and vanadium into ethyl ether are presented.
- Grain Refinement of Uranium by Alloying
- Binary alloys of uranium with 38 elements in the range 0.01 to 1.0 at.% were made. Three alloys having nominal compositions of 0.01, 0.1, and 1.0 at.% were made with most of the elements, and in addition, 12 ternary and quaternary alloys were made. The alloys were cast, rolled to 7/8-inch-diameter bars, heat treated, and examined for grain size.
- The thermal and electrical conductivities of zirconium and its alloys
- A report which intends to present an empirical formula, based on available experimental data, to correlate the thermal and electrical conductiviities of sirconium and sirconium alloys.
- Jacketing of Uranium for High-Temperture Service
- From introduction: "The work covered in this report is a portion of the experimental research undertaken for the design of a uranium-containing metallic fuel rod for operation in air at 1090 C...This report deals with that phase which involved the testing and evaluation of various metals as barrier costs between uranium alloys, and low-carbon steel. The work is of a preliminary nature and is concerned more with a comparison of the various barrier metals than with the acquisition of numerical data, e.g., diffusion coefficients."
- Engineering Properties of High-Density Concretes
- From summary: "Methods were developed for measuring various engineering properties of high-density concretes. Data are presented on selected thermal properties of a limonite-iron concrete and the mechanical properties of the limonite-iron concrete, a magnesium oxychloride concrete, and a Portland cement concrete containing steel punchings and shot (no limonite)."
- Topical Report on Refining of MgX and Other Uranium-Bearing Materials
- This report discusses a study which explores the effects of feed and acidity on extractive methods. From abstract: "Results from fractional precipitation of MgX from dilute sulfuric acid solutions indicate that, in the presence of sufficienct iron, phosphate is precipitated as ferric phosphate, and not as uranyl phosphate."
- Quarterly Progress Report on Refining of MgX and Other Uranium-Bearing Materials
- From abstract: "Results are presented of Scheibel column extraction tests with neutral ether on a variety of combinations of feed solutions...The effect of added iron was evaluated for a considerable number of process solutions and slurries. Arsenic was traced through both primary and secondary extraction stages in one test."
- Progress Report on Refining of MgX and Other Uranium-Bearing Materials
- 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.
- Progress Report on Nonaqueous Extractive Methods for Western Uranium Ores
- Abstract: "Dissolution of carnotite in several readily liquefiable gases, including ammonia, sulfur dioxide, chlorine, and nitrogen dioxide, was found to be negligible, even in the presence of uranium complexing agents. No low-boiling liquids have been found which will dissolve carnotite directly. Treatment with various sulfur chloride will convert carnotite to a form soluble in water or in certain organic solvents. Also, carnotite can be readily dissolved in HCl-acidified ethanol, methanol, or acetone. Amenability tests on nine western ores with HCl-methanol solvent indicated that uranium extractions greater than 90 per cent could be obtained if sufficient acid was used to insure some free acidity in the pregnant liquor. Temple Mountain and Sinbad-Muddy River ores were exceptions to this, uranium extractions being only about 50-60 per cent. Vanadium extractions were invariably lower than uranium extractions. Chemical analyses are presented for nine western ores."
- Identification of Slag Constituents from Uranium Metal Production Bombs
- Abstract: "X-ray and microscopic examination of slags from uranium metal production bombs which gave good and bad yields in the plant at St. Louis have indicated the significance of uranium oxide formation. Apparently the oxide (UO2) results from reaction of the UF4 with linear material, particularly with moisture in the liner."
- Use of electrical measurements to detect differences among uranium tetrafluoride samples : final report
- A report which contains a summary of the research during the period September 1, 1951, to January 31, 1952, on the utilization of electrical measurements to detect chemical and physical differences in various samples of UF4.
- The Determination of Rare Earths in Thorium
- Abstract: "A quantitative method for the determination of individual rare earths in thorium down to a level of 0.05 ppm, is described. The procedure consists of a chromatographic cellulose-columns separation followed by a solution-type spectrographic determination. Values are given for the recovery of a number of rare earths using this combined procedure."
- Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 1. Laboratory Investigations
- Report discussing laboratory investigations of thorium nitrate purification. Batch equilibrium data, solubility data, viscosity data, density data, and the results seven batch countercurrent extraction tests and two selective stripping tests are included.
- The Ammonium Carbonate Pressure Leaching of Uranium Ores Proposed as Feed to the Pilot Plant at Grand Junction, Colorado : Progress Report
- From introduction: This is Progress report BMI-282, the first of a series covering the operation of the pressure-leaching towers for the extraction of uranium by an ammonium carbonate leach...This report discusses the data obtained from tests run to show the effects of such variables as the amount of air and carbon dioxide passed through the pulp, temperature, pressure, and concentration of ammonium carbonate and ammonium bicarbonate in the leach solution on the extraction of uranium.
- Zirconium Research and Development : Progress Report
- From introduction: "This is the ninth monthly report, BMI-514, under Contract No. AT(30-1)-771 on "Zirconium Research and Development". The report covers the work period from September 15, 1950, to October 15, 1950. Work is continuing on the preparation of large-diameter zirconium crystal bars in the 16-inch-diameter de Boer unit. Crystal bars up to 1-5/16 inches in diameter and 8 feet long have been prepared in this unit."