Technical Report Archive & Image Library (TRAIL) - 192 Matching Results
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- Topical report on spectrophotometric determination of small amounts of uranium in phosphate rock, shales and similar materials
- A report which provides procedures for sample decomposition and the determination of small amounts of uranium in the phosphate rocks and shales. Also, the cupferron and ether-extraction methods are discussed.
- Beta-Counting Methods Applied to the Determination of Uranium in Low-Grade Ores
- The following report covers investigations on the application of the beta counter as an analytical tool for use in experiments on the extraction and concentration of uranium from low-grade (.005-.02 % uranium) shale and phosphate rock ores.
- Topical Report on Chemical Process to Recover Uranium from Phosphate Rock
- The following report summarizes research done on dissolving uranium from phosphate rock and superphosphate and recovering it from solution in a more concentrated form.
- 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
- 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.
- Topical report on examination of residues from the nitric acid digestion of pitchblende
- A report about an investigation started to determine the compounds and/or minerals present in the residue resulting from nitric acid digestion of ore. Emphasis was placed on determining the compounds and/or minerals containing boron.
- Progress Report on the Concentration of Pitchblende
- Abstract: "Additional work on the flotation of sulphides from high-sulphur pitchblende is described. Data needed for the selection of flotation equipment are presented."
- 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."
- 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."
- 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."
- 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."
- 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."
- 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.
- Progress Report on the Concentration of Pitchblende
- Abstract: "The results of leaching studies on sulphide froth products obtained from the flotation of high-sulphur pitchblende are presented. The distribution of molybdenum in flotation products is also given. The flotation test at Middlesex is evaluated."
- 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."
- The technology of thorium
- A report describing the technological uses of thorium. The report details interest in thorium as a potential source of the fissionable isotope U233 as well as possessing other applications. Most of the information in this report was obtained from project literature and from unpublished data available to the authors.
- 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.
- Mineralogical Examination of Pitchblende Concentrates and Nitric Acid Digest Residues
- This report has two parts to it discussing mineralogical examination of pitchblende concentrates and nitric acid digest residues. Part I gives the results of a cursory examination with the petrographic microscope of samples of pitchblende concentrates and residues to see if there is a relationship between the mineral composition of the samples and the filterability of the residue. Part II gives a revaluation of the data in Report BMI-241 on the mineral composition of two residues from the nitric acid digestion of pitchblende concentrates at the Rallinckrodt Chemical Works.
- The Preparation of Large-diameter Zirconium Crystal Bar by the De Boer Process
- This report discusses the production of large-diameter zirconium crystal bars in a 16 inch diameter, Hastelloy B, de Boer unit in order to increase production efficiency.
- 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)."
- 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.
- 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."
- 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."
- Zirconium Pilot Plant Research and Development Progress Report
- 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.
- 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.
- The Fabrication and Compatibility of Metallic Fuel Elements for High-Temperature Service
- From summary: "This report covers an experimental investigation into the fabrication of various potential fuel-element materials and the testing of these materials for compatibility with structural metals at 1090 C (2000 F)."
- Zirconium Pilot Plant Research and Development Progress Report
- The following report studies the effect of flow rates and deposition pressure on the zirconium deposition in the zirconium pilot plant with the use of a Hilco oil purifier for the vacuum pumps that permitted studies to continue through the month.
- The Rolling of Thorium Rod
- Report discussing the rolling of thorium rods. Abstract: "Thorium rods, 1-7/16 inch in diameter, were rolled from Ames castings. The billets were roughed down in diamond-grooved rolls and finished in hand-rounding rolls. Remelted chips as well as primary-metal castings were rolled, and both yielded satisfactory rods. The surface quality of the rods was generally excellent, and the machined slugs were free of seams."
- A Study of Thorium-Base Alloys
- Report discussing studies testing various thorium alloys consisting of either Ames thorium and up to 5% of various additions or Ames thorium and up to 50% uranium. Effects of molybdenum additions for fusion welding, and cold-work strengthening were also tested. Methods, experimental data, and discussion is included.
- 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.
- Tungsten-Arc Welding of Ames Thorium and Thorium Alloys
- This report follows an investigation made on the welding of Ames thorium by the inert-gas-shielded tungsten-arc process as the first part of a program on the joining of thorium. This program is part of a broader research program to develop the technology of thorium.
- 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."
- Progress Report for the Month of January, 1952
- This progress report of the Battelle Memorial Institute covers information in many categories. These include development of ceramic fuel elements, general ceramics, uranium and its alloys, thorium and its alloys, development of metallic fuel elements and assemblies, metals and alloys for reactor components, miscellaneous metallurgical work, liquid coolants and fuels, reactor engineering studies, and mechanism development.
- Progress Report for the Month of February, 1952
- This progress report of the Battelle Memorial Institute covers information in many categories for February, 1952. These include development of ceramic fuel elements, general ceramics, uranium and its alloys, thorium and its alloys, development of metallic fuel elements and assemblies, metals and alloys for reactor components, miscellaneous metallurgical work, liquid coolants and fuels, reactor engineering studies, and mechanism development.
- Hydroxides as Moderator Coolants in Power-Breeder-Reactors
- The following report describes work that was udertaken to determine whether a homogeneous breeder reactor using an alkili metal hydroxide solution is capable of breeding.
- 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."
- Alloys of Uranium with Zirconium, Chromium, Columbium, Vanadium, and Molybdenum
- Abstract: Information on five uranium binary alloy systems has been surveyed. These systems are the alloys of uranium with zirconium, chromium, columbium, vanadium, and molybdenum. The equilibrium diagrams are discussed, and where available, data have been included on diffusion studies, cladding experiments, and mechanical properties.
- Experimental Fabrication of a Lightweight Control Rod
- Abstract: "The possibility of fabricating a lightweight control rod from one of several high cross-section materials was investigated. The major effort was directed toward the development of a titanium-clad rod containing a composite core of 25 weight per cent Gd2O3 in a matrix of titanium. Experimentation on both subscale and full-scale control-rod cores showed that the fabricating behavior of the two was not analogous. To roll the full-scale core successfully, it was necessary to lower the oxide content to 17 weight per cent. Subscale investigations were also carried out on titanium-cadmium, titanium-lanthanum, and titanium-gadolinium alloys."
- Beryllia and Beryllia-Beryllium Bodies for Moderating Cores in Fuel Elements
- From introduction: This report presents the results of the two phases of the work: study of the compatibility of beryllia bodies with a coating material, molybdenum; and studies of beryllia-beryllium body fabrication.
- 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.
- Final Report on Purification of Thorium Nitrate by Solvent Extraction With Tributyl Phosphate: 2. Mixer-Settler Pilot Plant Investigations
- From abstract: "This report describes the construction and operation of a mixer-settler pilot plant for the purification of mantle-grade thorium nitrate. The liquid-liquid extraction process utilized 30% tributyl phosphate - 70% 'Solvesso-100' as the organic solvent and nitric acid as the salting agent. Continuous steady-state operation of the equipment was demonstrated, with very good recovery of thorium."
- An Application of the Concepts of Particle Packing to the Consolication of Silicon Carbide Powders
- From introduction: Silicon carbide is being considered as a basis material for nonmetallic fuel elements because of its high thermal conductivity, low nuclear cross section, high resistance to thermal rupture, and high degree of stability at high temperature in air. A requirement of the fuel elements is that they be thin and have as low porosity as possible. One shape of element under consideration is 0.050 to 0.070 inch thick by a few inches in width and breadth.
- Hydrogen Embrittlement of Zirconium
- Abstract: "The amount of hydrogen normally present in zirconium and zirconium alloys suffices to reduce their ductility greatly in an impact test at room temperature, after slow cooling from 600 F. Quenching from 600 F or above gives high impact strength, as does removal of hydrogen by high-temperature vacuum annealing. This report discusses the evidence on hydrogen embrittlement, the diffusion, solid solubility, and equilibrium pressure of hydrogen of hydrogen in zirconium, the microstructure, and the effects of hydrogen and heat treatment on the mechanical properties of zirconium."
- Creep of 2S-O Aluminum Sheet at 500 and 550 C
- 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."
- 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."
- 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."