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The Reactivity of Uranium and Blacosolv (open access)

The Reactivity of Uranium and Blacosolv

Abstract: "Blacosolv, trichloroethylene, is used in degreasing uranium metal. Tests were made under possible industrial conditions to determine whether a hazardous reaction between uranium and Blacosolv could occur. Temperature-rise measurements showed that there was no reaction of the metal, in various states of subdivision, with Blacosolv at temperatures up to 850 F. However, a reaction was observed in tests under which the finely divided metal, wet with solvent, was subjected to a severe impact."
Date: January 21, 1955
Creator: Hannan, H. D.; Miller, P. D. & Peoples, R. S.
Object Type: Report
System: The UNT Digital Library
A Study of Aluminum-Uranium Alloys (open access)

A Study of Aluminum-Uranium Alloys

Report discussing the redetermination of liquids for aluminum alloys containing 13 to 25 w/o uranium by metallographic examination, thermal analyses, and electrical resistance measurements. In addition, phase diagrams and a method for producing sound, homogeneous aluminum 16 w/o uranium alloy sleeve castings are presented.
Date: January 19, 1956
Creator: Saller, Henry A.; Dickerson, Ronald F.; Rough, Frank A.; Foster, Ellis L.; Bauer, Arthur A. & Lulay, John R.
Object Type: Report
System: The UNT Digital Library
The Properties of Uranium Containing Minor Additions of Chromium, Silicon, or Titanium (open access)

The Properties of Uranium Containing Minor Additions of Chromium, Silicon, or Titanium

This report discusses a study regarding the properties of uranium with added chromium, silicon, or titanium. This study was conducted in order to evaluate the effects of alloying on the mechanical properties of base metal.
Date: January 30, 1956
Creator: Saller, Henry A.; Rough, Frank A. & Chubb, Walston
Object Type: Report
System: The UNT Digital Library
A Study of Internal Friction and Twin-Boundary Movement in Uranium (open access)

A Study of Internal Friction and Twin-Boundary Movement in Uranium

From abstract: "The internal friction of recrystallized uranium has been shown to depend directly on heating and cooling rates and on the rate of application or removal of an external stress during measurement. At zero heating or stress rate, the internal friction falls to a low value and appears to decrease indefinitely at room temperature. Micrographs showing twin disappearance on removal or reversal of load are shown...It is concluded that the various internal-friction phenomena are the result of the stress-induced motion of twin boundaries." Results are compared with similar studies as well.
Date: January 30, 1956
Creator: Maringer, Robert E.; Marsh, Lyle L. & Manning, George K.
Object Type: Report
System: The UNT Digital Library
Polarographic Analysis of UNH in the IAW Stream (open access)

Polarographic Analysis of UNH in the IAW Stream

The following report describes two rapid, micro methods for the determination of UNH in Redox waste samples that had been developed fir the concentration range 0.2 to 100 g/l.
Date: January 17, 1949
Creator: Alkire, G. J. & Carson, W. N.
Object Type: Report
System: The UNT Digital Library
Nuclear Reactor Project Progress Report, January 1948 (open access)

Nuclear Reactor Project Progress Report, January 1948

This report is a progress report detailing operations and ongoing projects at the Brookhaven National Laboratory. The report describes new developments with buildings and progress regarding ongoing experiments. The report includes photographs showing progress in the construction of the reactor and other images and figures that accompany the descriptions of projects.
Date: January 1, 1948
Creator: Borst, L. B. & Fox, Marvin
Object Type: Report
System: The UNT Digital Library
Uranium Chemistry of Raw Materials Section Progress Report for October 1, 1951 to December 31, 1951 (open access)

Uranium Chemistry of Raw Materials Section Progress Report for October 1, 1951 to December 31, 1951

This progress report discusses the work during the fourth quarter of 1951. During this quarter, "the uranium raw materials program at ORNL has been devoted to studies of uranium chemistry and to the development of processes for deriving uranium and byproducts from various types of ores" (From introduction).
Date: January 25, 1952
Creator: Brown, K. B.
Object Type: Report
System: The UNT Digital Library
Stable Isotope Research and Production Division Quarterly Progress Report: October 1, 1951 to December 31, 1951 (open access)

Stable Isotope Research and Production Division Quarterly Progress Report: October 1, 1951 to December 31, 1951

From introduction: "During the second quarter of fiscal year 1952, the Isotope Production and Process Development Department placed primary emphasis on the collection of lithium, iron and calcium isotopes."
Date: January 2, 1952
Creator: Keim, C. P. & Walton, J. R.
Object Type: Report
System: The UNT Digital Library
Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber (open access)

Calorimetric Calibration of a Graphite Walled, Cavity-Type Ionization Chamber

Technical report outlining cavity-type ionization chambers with graphite walls that are used to measure heat dissipation in the graphite reflector of the MTR mock-up. Studies the relationship between the ionization occurring in the chamber and the heat generated in the surrounding graphite medium. [From Abstract]
Date: January 23, 1951
Creator: Jenks, G. H.; Breazeale, W. M. & Hairston, J. J.
Object Type: Report
System: The UNT Digital Library
Studies on the Removal of Radioisotopes From Liquid Wastes by Coagulation (open access)

Studies on the Removal of Radioisotopes From Liquid Wastes by Coagulation

Technical report covering work completed on the removal of radioisotopes from water using a calcium phosphate floc as a carrier. This research was performed as part of the Health Physics Waste Disposal Research Section work on the removal of small quantities of radioactivity from large volumes of water. [From Abstract]
Date: January 23, 1951
Creator: Lauderdale, Robert A., Jr.
Object Type: Report
System: The UNT Digital Library
The Corrosion of Hot-Pressed, Extruded, and Vacuum Cast Beryllium in Simulated Cooling Water for the Materials Testing Reactor (open access)

The Corrosion of Hot-Pressed, Extruded, and Vacuum Cast Beryllium in Simulated Cooling Water for the Materials Testing Reactor

Technical report covering the technology of hot-pressed beryllium production and its rapid advancement toward the end of 1949. Part I is devoted to corrosion studies made on hot-pressed and vacuum cast extruded metal which was considered representative of production. Part II is concerned with the results of tests made on special cast and hot-pressed beryllium which contained added impurities. [From Introduction]
Date: January 9, 1953
Creator: Reed, James
Object Type: Report
System: The UNT Digital Library
Physics Division Quarterly Progress Report for Period Ending September 20, 1950 (open access)

Physics Division Quarterly Progress Report for Period Ending September 20, 1950

Technical report covering experiments to measure the resonance and absorption of neutrons in U238 cylinders. Report also discusses control problems connected to the Bulk Shielding Facility and work on MTR controls.
Date: January 8, 1951
Creator: Sneil, A. H. & Wollan, E. O.
Object Type: Report
System: The UNT Digital Library
The Angular Dependence of Thermal Neutron Spectra in Lattices (open access)

The Angular Dependence of Thermal Neutron Spectra in Lattices

This technical report discusses techniques that have been developed for "computing the angular thermal flux spectrum emerging from a lattice. These methods are applied to water lattices and it is found that the computed spectra are sensitive to the geometrical description of the lattice, but insensitive to the anisotropic scattering by water. Comparisons with measured spectra indicate that corrections for gradients and the finite size of the experimental lattice are important." -- from abstract (p. 3).
Date: January 1962
Creator: Honeck, Henry C. & Takahashi, Hiroshi
Object Type: Report
System: The UNT Digital Library
Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity (open access)

Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity

From Abstract: "The diffusion cooling coefficient in graphite has been determined by measuring the change in the asymptotic average velocity with buckling, by pulsed neutron methods. The times necessary to establish equilibrium spectra in graphite and heavy water have been measured and are reported."
Date: January 2, 1962
Creator: Starr, E. & De Villiers, J. W. L. (Jacobus Wynand Louw)
Object Type: Report
System: The UNT Digital Library
Solid State Division Quarterly Progress Report: August 1952 (open access)

Solid State Division Quarterly Progress Report: August 1952

This quarterly progress report discusses the ongoing work within the Solid State Division at the Oak Ridge National Laboratory for the period ending August 10, 1952. Projects discussed include radiation metallurgy, engineering properties, fused salts, crystal physics, and solid state reactions.
Date: January 30, 1959
Creator: Billington, D. S. (Douglas S.) & Howe, J. T.
Object Type: Report
System: The UNT Digital Library
The Supercritical Water Reactor (open access)

The Supercritical Water Reactor

From summary: "During 1951 NDA has, at the request of ORNL, been studying the supercritical-water reactor as proposed for aircraft propulsion in Wash-24...This study has concerned itself only with the reactor and shield." The report describes the reactor and the processes involved in developing it. The goal of the development of this reactor is identified as a path to supersonic flight.
Date: January 2, 1952
Creator: Nuclear Development Associates, Inc.
Object Type: Report
System: The UNT Digital Library
The Reaction Between Hydrogen and Oxygen by Catalysis and the Thermal Reaction (open access)

The Reaction Between Hydrogen and Oxygen by Catalysis and the Thermal Reaction

From abstract: "The reaction between hydrogen and oxygen with the aid of various catalysts (especially platinum on aluminua) has been studied, and the operating variables such as flow rates, space velocity, temperature, and gas composition have been examined rather extensively. It has been found that hydrogen and oxygen in stoichiometric proportions and mixed with either steam or helium may be made to react to the extent of 99.5% or greater at space velocities up to 30,000 hr-1, or even higher, at temperatures from 100[degrees] to 900[degrees]C, and with mixtures ranging from less than 1% hydrogen to mixtures containing 12% hydrogen and 6% oxygen. Richer mixtures, including undiluted electrolytic gas (H2 + 1/2 O2) have been used with catalysts less active than platinum (e.g. copper, silver, nickel and V2O5) but here the gas mixture is explosive and care must be taken to prevent explosions. The thermal reaction between hydrogen and oxygen diluted with steam has also been investigated at temperatures between 500[degrees] and 800[degrees]C."
Date: January 15, 1952
Creator: Kuhn, D. W.; Ryon, A. D.; Palko, A. A. & Clewett, G. H.
Object Type: Report
System: The UNT Digital Library
A Manual of HRE Control and Instrumentation (open access)

A Manual of HRE Control and Instrumentation

Technical reports outlining the controls for the Homogeneous Reactor Experiment (HRE); controls are divided into three principal groups. 1. Reactor. 2. Process or auxiliary. 3. Power generation. These are the classifications designating the primary functions of the controls. [From Introduction]
Date: January 23, 1952
Creator: Quarles, L. R. & Walker, W. P.
Object Type: Report
System: The UNT Digital Library
Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending September 10, 1951 (open access)

Aircraft Nuclear Propulsion Project Quarterly Progress Report: Period Ending September 10, 1951

The first part of this quarterly progress report details reactor theory and design, discussing the aircraft reactor experiment, experimental reactor engineering, reactor physics, and critical experiments. The second part of this report is not included. The third part of this quarterly progress report details materials research, discussing corrosion research, physical properties and heat-transfer research, metallurgy and ceramics, chemistry of high-temperature liquids, and radiation damage. The fourth part of this quarterly progress report details alternate systems, discussing a supercritical water reactor, circulating-moderator-coolant reactors. The fifth part of this quarterly progress report includes appendixes.
Date: January 9, 1952
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, William B.
Object Type: Report
System: The UNT Digital Library
Nuclear Decay Schemes of Some of the Isotopes of Tantalum (Master's Thesis) (open access)

Nuclear Decay Schemes of Some of the Isotopes of Tantalum (Master's Thesis)

This report discusses a nuclear spectroscopic study of the radiations resulting from the electron capture decay of Ta-176, Ta-177, and Ta-178, analyzing data of nuclear decay schemes.
Date: January 25, 1956
Creator: Felber, Frank Frederick, Jr.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Excitation Functions for Reactions of Bev Protons on Indium (Master's Thesis) (open access)

Excitation Functions for Reactions of Bev Protons on Indium (Master's Thesis)

Abstract: "Indium was bombarded with protons in the energy range 2 to 6 Bev. Cross sections are reported for the (p,px+), (p,pn), and (p,p') reactions, as well as those for the formation of Be-7 and several neutron deficient isotopes of cadmium and indium. It was found that the (p,pn) yield increases slowly in the energy range 2 to 6 Bev, while the (p,px+) and (p,p') yields are approximately constant. The variation of the (p,pn) and (p,px+) yields with target thickness is discussed. The yields of several isomeric levels are correlated with their nuclear spin."
Date: January 1957
Creator: Nethaway, David Robert
Object Type: Report
System: The UNT Digital Library
Off-Gas Treatment in Berkeley Enclosures (open access)

Off-Gas Treatment in Berkeley Enclosures

"In the past ten years quantities of alpha-, beta-, gamma- and neutron-emitting isotopes handled in enclosures have increased from microcuries to kilocuries. Contaminated-atmosphere problems have increased accordingly. Developments at Berkeley are reviewed with particular emphasis on recent equipment, viz: a multiple-purpose gas scrubber and a total-capture system for slug-dissolver off gas."
Date: January 7, 1957
Creator: Thaxter, M. D.; Cantelow, H. P. & Burk, C.
Object Type: Report
System: The UNT Digital Library
An "Exact" Analysis of a Cylindrical Plasma in a Magnetic Field (open access)

An "Exact" Analysis of a Cylindrical Plasma in a Magnetic Field

Abstract: "The analysis of an immobilized plasma is here extended to the case where the geometry is cylindrical rather than Cartesian. (This report, UCRL-4439 (Rev, 4 constitutes Part II of the report series (UCRL-4466, Parts I, III, and IV) dealing with this general problem.)"
Date: January 14, 1955
Creator: Tonks, Lewi, 1897-1971
Object Type: Report
System: The UNT Digital Library
Interim Report on Examination of Powder Metallurgy Slug from PT-105-313-4M (open access)

Interim Report on Examination of Powder Metallurgy Slug from PT-105-313-4M

This report examines a uranium slug that has been produced by powder metallurgical methods and exposed in the 100-DR Pile and was deformed during pile exposure.
Date: January 5, 1953
Creator: O'Keefe, D. P.
Object Type: Report
System: The UNT Digital Library