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Exploratory Scavenging Studies for the Decontamination of Redox Solutions (open access)

Exploratory Scavenging Studies for the Decontamination of Redox Solutions

From introduction: "This report is concerned with exploratory experiments designed to studies the efficiency of a number of scavengers for zirconium and niobium adsorption and to provide preliminary information on the best conditions to employ on the most satisfactory of those scavengers studied, namely Super Filtrol FO. The data in this report include data obtained through October, 1949, and are by no means considered to be final. The investigation is currently being actively continued."
Date: May 1, 1950
Creator: Roake, W. E. & Lowe, C. S.
Object Type: Report
System: The UNT Digital Library
Equilibrium Relationships for Stripping Uranium from Solutions of Tributyl Phosphate and Hydrocarbon Diluent (open access)

Equilibrium Relationships for Stripping Uranium from Solutions of Tributyl Phosphate and Hydrocarbon Diluent

Objective: "The laboratory equilibrium study RC-E-1 described in this report was carried out to obtain uranium equilibrium curves at various concentrations of nitric acid and of TBP."
Date: May 1, 1950
Creator: Clagett, Fred
Object Type: Report
System: The UNT Digital Library
Creep Strength of Uranium Alloys at 1500 and 1800 F (open access)

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."
Date: May 28, 1953
Creator: Saller, Henry A.; Stacy, J. T.; Eddy, N. S. & Klebanow, H. L.
Object Type: Report
System: The UNT Digital Library
Electroplated Metals on Uranium for Aluminum Cladding (open access)

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."
Date: May 4, 1955
Creator: Beach, John G.; Schickner, William C.; Hopkinson, Dolores. & Faust, Charles L.
Object Type: Report
System: The UNT Digital Library
Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Heat Treatment (open access)

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."
Date: May 13, 1955
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, Arthur A.
Object Type: Report
System: The UNT Digital Library
Low-Melting Alloys for Cast Fuel Elements (open access)

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.
Date: May 19, 1955
Creator: Saller, Henry A.; Rough, Frank A. & Bauer, Arthur A.
Object Type: Report
System: The UNT Digital Library
An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building (open access)

An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building

Abstract: "An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fallout. Pocket ionization chambers were used for measurement of the radiation-field strength. Fallout was simulated with distributed and point-source configurations of Co-60 and Ir-192 sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation."
Date: May 1, 1959
Creator: Batter, J. F., Jr.; Kaplan, A. L. & Clarke, Eric Thacher
Object Type: Report
System: The UNT Digital Library
Separation of Small Amounts of Scandium From Uranium (open access)

Separation of Small Amounts of Scandium From Uranium

Abstract: A method for separating small amounts of scandium (1 to 10 mg.) from a gram of uranium depends upon formation of insoluble uranium peroxide while the scandium in solution is complexed with ethylenediamine-tetraacetic acid. The precipitated peroxide carries down less than 30 p.p.m. of scandium. Uranium left in solution, less than one milligram in amount, does not interfere when the scandium is precipitated as ammonium scandium tartrate and determined gravimetrically by ignition of the tartrate to the oxide.
Date: May 1954
Creator: Bergstresser, Karl S.
Object Type: Report
System: The UNT Digital Library
Proposed Electron Probe of the Discharge Current in the Perhapsatron (open access)

Proposed Electron Probe of the Discharge Current in the Perhapsatron

Report discussing a proposed electron probe that is connected to the discharge current from a device called the Perhapsatron. "The Perhapsatron is an apparatus for the study of the type of magnetic containment known as the 'pinch effect.'"
Date: May 1954
Creator: Dunaway, R. E. & Phillips, J. A.
Object Type: Report
System: The UNT Digital Library
Determination of Hydrogen in Lithium Hydride (open access)

Determination of Hydrogen in Lithium Hydride

Abstract: "A method for determining hydrogen in lithium hydride by heating samples with lead at 600 C, was developed. The hydrogen evolved during thermal decomposition of the hydride is purified and oxidized to water with cupric oxide at 400 C. The analysis is completed by collecting and weighing this water. Success in development of the analytical procedure has depended upon a careful design and assembly of equipment for handling samples in a dry, inert atmosphere. For seven pure hydride samples analyzed by the recommended method the estimates of the standard deviation varied between 0.12 and 0.41 percent lithium hydride (or 1.3 and 4.2 parts per thousand) for 8 to 18 determinations on each sample. The procedure is relatively insensitive to variations in certain conditions. For single-piece samples weighing 0.2 to 0.5 gram it was found to be more satisfactory than a method which uses mercury in place of lead for sample decomposition. For powdered lithium hydride samples the lead and mercury methods are equally satisfactory."
Date: May 1954
Creator: Bergstresser, K. S. & Waterbury, Glenn R.
Object Type: Report
System: The UNT Digital Library
Improved Zirconium Alloys: Monthly Report 12, April 1961 (open access)

Improved Zirconium Alloys: Monthly Report 12, April 1961

Monthly report the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between April 1 to April 31, 1961 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: May 4, 1961
Creator: Weinstein, Daniel & Holtz, F. C.
Object Type: Report
System: The UNT Digital Library
Engineering Properties of High-Density Concretes (open access)

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)."
Date: May 1951
Creator: Snyder, M. Jack; Burkart, C. A. & Clegg, John W.
Object Type: Report
System: The UNT Digital Library
The Determination of Rare Earths in Thorium (open access)

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."
Date: May 15, 1952
Creator: Center, E. J.; Henry, W. M. & Householder, R. D.
Object Type: Report
System: The UNT Digital Library
Identification of Reaction Products Formed During Magnesium Reduction of Uranium Tetrafluoride: Report (open access)

Identification of Reaction Products Formed During Magnesium Reduction of Uranium Tetrafluoride: Report

Abstract: "This report describes the results of X-ray diffraction examination of reaction products from a series of experiments performed by Mallinckrodt Chemical Works as an acid in understanding the process of bomb reduction of UF4. UF4 is initially reduced to UF3 by magnesium at 560 C., and subsequently to metal at 600 C. MgF2 from the initial reaction forms a coating on the magnesium which retards the final spontaneous reaction."
Date: May 15, 1953
Creator: Schwartz, C. M. & Vaughan, D. A.
Object Type: Report
System: The UNT Digital Library
The Neutron Energy Distribution in the Center of the Los Alamos Plutonium Reactor (open access)

The Neutron Energy Distribution in the Center of the Los Alamos Plutonium Reactor

The following report examines the fission counter, fission plates and activation results of the neutron energy distribution in the center of the Los Alamos plutonium reactor.
Date: May 12, 1948
Creator: Hall, Jane H.; Hall, David B.; Spano, Alfred; Williams, Clarke & Griffin, David L.
Object Type: Report
System: The UNT Digital Library
Effect of Temperature and Reactivity Changes in Operation of the Los Alamos Plutonium Reactor (open access)

Effect of Temperature and Reactivity Changes in Operation of the Los Alamos Plutonium Reactor

The operation of the Fast Reactor is considered in terms of normal equilibrium conditions and normal shut-down. The proposed loading, control rod adjustment and subsequent "floating" operation are discussed. Safety devices and interlocks are described. Temperature and reactivity changes are examined with respect to various system failures, phase changes, and "flashing" of the reactor. Slow changes due to faulty slug cooling are also considered. The calculations were initially based upon 10 kw operation. Performance tests of the mercury system now indicate that 20-kw operation may be feasible.
Date: May 28, 1948
Creator: Hall, David B. & Hall, Jane H.
Object Type: Report
System: The UNT Digital Library
The Decontamination of Uranium from Fission Products by the Use of the Uranyl Oxalate Precipitation Reaction (open access)

The Decontamination of Uranium from Fission Products by the Use of the Uranyl Oxalate Precipitation Reaction

Abstract: "Decontamination factors of the order of 10-4 were obtained for Beta and Gamma emitters present as fission products when uranium was precipitated from 50 mC activity level solutions as uranyl oxalate under normal uranium yield conditions for three cycles (~60%). Factors of the order of 10-3 were obtained by the use of this reaction with similar solutions under relatively high uranium yield conditions for three cycles (~90%). The uranium peroxide precipitation reaction proved to be of no value on such solutions, yielding decontamination factors of only 17.1 Beta emitters and 1.2 for Gamma emitters for three cycles."
Date: May 10, 1951
Creator: Kelchner, B. L.
Object Type: Report
System: The UNT Digital Library
Determination of Particle Size Distribution and Surface Area by Photometry (open access)

Determination of Particle Size Distribution and Surface Area by Photometry

The following report describes procedures taken to utilize the photelometer to procure the most rapid and reliable determinations, but the goal of the tests presented was to create satisfactory dispersions of particles to analyze.
Date: May 13, 1948
Creator: King, D. R. & Panowski, J. B.
Object Type: Report
System: The UNT Digital Library
Magnetic Properties of Insulators : Quarterly Report No. 1 Covering the Period from February 15, 1961 to May 15, 1961 (open access)

Magnetic Properties of Insulators : Quarterly Report No. 1 Covering the Period from February 15, 1961 to May 15, 1961

"The magnetic properties of color centers were studied to obtain information regarding electron traps in insulators. Experiments designed to determine the equation governing the recovery of resonance after saturation were carried out. Relatively large samples were prepared by the method of additive coloration. KCl and RbCl crystals were used. Resonance saturation as a function of concentration was investigated and no significant dependence found. Measurements of the unsaturated susceptibility were made at liquid nitrogen and liquid helium temperatures. The bleaching of the F-center to form the B-band produced a different resonance. The equipment for observing the saturation and recovery of a portion of the resonance at 4 deg K is described. A theoretical examination was made of the interaction between the vibration of the ions around a negative-ion vacancy in an alkali halide and an electron trapped at that site. (M.C.G.)."
Date: May 29, 1961
Creator: Markham, Jordan J.
Object Type: Report
System: The UNT Digital Library
Niobium Phase Diagrams : Manuscript Report on Niobium-Carbon System (open access)

Niobium Phase Diagrams : Manuscript Report on Niobium-Carbon System

Abstract: "The niobium-carbon system has been determined by X-ray and metallographic examination of sintered and arc-cast alloys. Two carbides exist: hexagonal Nb2C with a limited range of homogeneity, and cubic NbC with a solubility range from 8.25 to 10.25 weight per cent carbon. Dilute alloys freeze by eutectic reaction at 2230 C. The solubility of carbon in niobium is 0.80 at the eutectic temperature, but this decreases rapidly with temperature. Metallographic evidence indicates a peritectic reaction between melt, Nb2C, and NbC; alloys richer in carbon than NbC freeze by eutectic reaction."
Date: May 6, 1959
Creator: Elliott, Rodney P.
Object Type: Report
System: The UNT Digital Library
Niobium Phase Diagrams (open access)

Niobium Phase Diagrams

The following report is the final technical report on a series of reports under contract AT(11-1)-515, titled "Niobium Phase Diagrams", covering the period from April 15, 1957 to April 16, 1960.
Date: May 15, 1960
Creator: Elliott, Rodney P. & Komjathy, Steven
Object Type: Report
System: The UNT Digital Library
Electroplated Metals on Uranium (open access)

Electroplated Metals on Uranium

The following report follows the studies of electroplating on uranium and concurrent metallurgical clodding.
Date: May 7, 1954
Creator: Beach, John G.; Schickner, W. C.; Konecny, C. R. & Faust, Charles L.
Object Type: Report
System: The UNT Digital Library
Properties of Stainless Steel-Uranium Dioxide Fuel Plates (open access)

Properties of Stainless Steel-Uranium Dioxide Fuel Plates

From abstract: "A method for fabricating 30-in.-long stainless steel - uranium dioxide sheet was developed and the properties of the fabricated sheet were investigated."
Date: May 11, 1954
Creator: Keeler, J. R. & Cuddy, L. J.
Object Type: Report
System: The UNT Digital Library
Investigation of Methods for End Capping Stainless Steel Pins (open access)

Investigation of Methods for End Capping Stainless Steel Pins

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.
Date: May 18, 1956
Creator: Vagi, Julius J.; Thompson, Harold B. & Martin, David C.
Object Type: Report
System: The UNT Digital Library