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Welded Repair of Fill and Drain Holes in High-Carbon Steel Gas Storage Cylinders (open access)

Welded Repair of Fill and Drain Holes in High-Carbon Steel Gas Storage Cylinders

Report discussing the results of fill and drain holes for hydrostatic pressure tests on head knuckle radius of forged-steel gas storage cylinders.
Date: November 5, 1964
Creator: Thompson, J. C. & Lambert, F. J.
Object Type: Report
System: The UNT Digital Library
PRTR second generation shim assembly (open access)

PRTR second generation shim assembly

From introduction: "This document discusses the design, fabrication, assembly, and testing of a second generation shim rod assembly, and testing of a second generation shim rod assembly prototype for use in the Plutonium Recycle Test Reactor."
Date: November 1964
Creator: Rasmussen, D. E.
Object Type: Report
System: The UNT Digital Library
The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements (open access)

The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements

The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.
Date: November 1, 1961
Creator: Stein, P. E.; Ayers, A. C.; Braatz, R. J.; Bradford, C. M.; Holt, V. D. & Mattie, G. P.
Object Type: Report
System: The UNT Digital Library
Production of Zirconium at Y-12 (open access)

Production of Zirconium at Y-12

Abstract: "A general description is given of the permanent zirconium plant at Y-12. Equipment is described and materials of construction are listed. Photographs illustrating principal equipment and reduced construction drawings are also presented. Operating conditions and costs information are listed."
Date: November 17, 1955
Creator: Ramsey, J. W. & Whitson, W. K., Jr.
Object Type: Report
System: The UNT Digital Library
Status Report and Plant Proposals for Zirconium Purification (open access)

Status Report and Plant Proposals for Zirconium Purification

From abstract: "This report contains a summary of the latest improvements in zirconium purification as developed by the Y-12 research, pilot plant, production, and engineering groups, all of whom have been generously cooperating in this project."
Date: November 18, 1955
Creator: Leaders, W. M.
Object Type: Report
System: The UNT Digital Library
Separation of Zirconium & Hafnium : Proposal for Construction & Operation of Zirconium Production Plant (open access)

Separation of Zirconium & Hafnium : Proposal for Construction & Operation of Zirconium Production Plant

Abstract: A re-evaluation of the cost of producing essentially hafnium free zirconium as zirconium oxide at a rate of 150,000-200,000 pounds zirconium per year by solvent extraction of the metal thiocyanates in a permanent plant has been made. Using part of the present temporary facilities, the cost, with five year amortization of the plant, will be $3.15 per pound zirconium. A by-product of the mixed oxides of hafnium and zirconium, having at least fifty percent hafnium and perhaps as high as ninety percent hafnium, can be made available with little additional cost.
Date: November 17, 1955
Creator: Googin, J. M. & Strasser, G. A.
Object Type: Report
System: The UNT Digital Library
Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report (open access)

Zirconium-Hafnium Separation : Mixer-Settler Studies : Final Report

Abstract: Use of the mixer-settler apparatus as a rapid means of determining improved conditions for plant operation is described including the experimental details. The preparation of highly purified samples of both zirconium oxide and hafnium oxide is discussed. (This document is concerned almost entirely with explorations of small scale continuous systems. Another document dealing with this general problem using small scale batch operations is being published simultaneously. It should prove of advantage to the reader to study this companion report, Document Y-611, by Barton, Overholser, and Grimes, to obtain a complete picture of the available information.).
Date: November 17, 1955
Creator: Waldrop, F. B.; Ward, W. T. & Leaders, W. M.
Object Type: Report
System: The UNT Digital Library
A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal (open access)

A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal

From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.
Date: November 30, 1962
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Nuclear Metals Annual Progress Report: 1956-1957 (open access)

Nuclear Metals Annual Progress Report: 1956-1957

Annual report for the U.S. Atomic Energy Commission Research Division describing work completed by programs at Nuclear Metals, Inc.
Date: November 20, 1957
Creator: Nuclear Metals, Inc.
Object Type: Report
System: The UNT Digital Library
Nuclear Port Survey of the State of New York (open access)

Nuclear Port Survey of the State of New York

Report of the capabilities of the state of New York to construct and service atomic propelled vessels and to handle the shipment of packaged radioactive materials, including used nuclear fuels.
Date: November 1961
Creator: Ebasco Services Incorporated
Object Type: Report
System: The UNT Digital Library
Site Attenuation (open access)

Site Attenuation

Abstract: Site attenuation is a measure of performance of an open test site used at frequencies below about 1 GHz for antenna calibration and equipment emission and susceptibility testing. These sites typically consist of a large, obstruction-free ground plane and the hemisphere above it. Site attenuation of an ideal site is calculated and compared to data measured using the 30 m by 60 m NBS ground screen.
Date: November 1985
Creator: FitzGerrell, R. G.
Object Type: Report
System: The UNT Digital Library
Conceptual Design and Economic Evaluation of a Steam-Cooled Fast Breeder Reactor (open access)

Conceptual Design and Economic Evaluation of a Steam-Cooled Fast Breeder Reactor

From abstract: This report describes a conceptual design and economic evaluation of 300 and 40 MWe steam-cooled fast breeder reactor power plants performed by NDA under contract with the AEC.
Date: November 15, 1961
Creator: Sofer, G.; Hankel, R.; Goldstein, L. & Birman, G.
Object Type: Report
System: The UNT Digital Library
Survey of Materials for Supercritical-Water Reactor (open access)

Survey of Materials for Supercritical-Water Reactor

Survey of properties of materials which might be suitable for use in various locations in a supercritical-water reactor. Properties examined include tensile strength, rupture strength, endurance strength, Young's modulus, tensile elongation, coefficient of thermal expansion, coefficient of thermal conductivity, density, nominal composition, usual heat treatments and thermal-neutron-absorption cross sections.
Date: November 27, 1953
Creator: Udy, Murray C. & Boulger, Francis W.
Object Type: Report
System: The UNT Digital Library
Electromagnetic Research Division Quarterly Progress Report, Part I for Period Ending June 30, 1952 (open access)

Electromagnetic Research Division Quarterly Progress Report, Part I for Period Ending June 30, 1952

From abstract: "On the 86-inch cyclotron a 41-kw beam has been calorimetered at a net ion loading efficiency of 40%; the average proton current was 1.85 ma at 22.5 Mev. Practical specific yields have been determined for (p,2n) reactions on zinc and bismuth. The investigation of products of proton-induced fission of uranium has been continued and new techniques are being used in measuring angular distribution of reaction products. The 63-inch heavy particle cyclotron is now in operation; N+++ particles have been accelerated to ~25 Mev. In preliminary tests, induced activities have been detected in carbon, nitrogen, and oxygen targets. A hot-cathode ion source is ready for test operation. The 22-inch cyclotron is being used in an investigation of the problems associated with the use of rf and dc electrodes for the acceleration of protons from the ion source into the dees. Radiation-induced corrosion in Inconel tubing containing #21 eutectic (ANP) has been produced by proton irradiation in the 86-inch cylclotron; it is shown that the corrosion was not due to thermal effects. Approximately 150 grams of highly purified U 238 (< 5 ppm U 235) have been prepared, and two grams of thorium 230 (ionium) has been enriched to 90.6%."
Date: November 14, 1952
Creator: Livingston, Robert S. & Howard, F. T.
Object Type: Report
System: The UNT Digital Library
The Escape of Fission Products From an Uranium Rod; Application to the B. N. L. Reactor (open access)

The Escape of Fission Products From an Uranium Rod; Application to the B. N. L. Reactor

Technical report covering the functions of the Oak Ridge reactor, difficulties encountered with cartridge failures in the Oak Ridge reactor, and possible solutions including the incorporation of leak detection systems into the design of the reactor.
Date: November 3, 1968
Creator: Chernick, J. & Kaplan, I.
Object Type: Report
System: The UNT Digital Library
Aerial Gamma Ray and Magnetic Survey, Volume 2. Final Report: Elk City Quadrangle of Idaho/Montana (open access)

Aerial Gamma Ray and Magnetic Survey, Volume 2. Final Report: Elk City Quadrangle of Idaho/Montana

Second volume of a report documenting a high-sensitivity airborne radiometric and magnetic survey of the Elk City quadrangle including a detailed geologic summary, interpretation report, standard deviation maps, pseudo-contour maps, interpretation maps, flight line and geologic base map, and individual corrected profiles.
Date: November 1979
Creator: EG & G GeoMetrics
Object Type: Report
System: The UNT Digital Library
Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds (open access)

Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds

Abstract: Technical report describing an evaluation of solvents for use in the extraction of uranium from Mallinckrodt type ore feeds.
Date: November 6, 1950
Creator: Runion, T. C.
Object Type: Report
System: The UNT Digital Library
Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds (open access)

Evaluation of Alternate Solvents for Diethyl Ether in the Extraction of Uranium From Mallinckrodt Type Ore Feeds

Technical report evaluating solvents for use in the extraction of uranium from Mallinckrodt type ore feeds. Re-evaluates the Mallinckrodt process in the light of the more recent solvent extraction development that has been carried out at various AEC sites.
Date: November 6, 1950
Creator: Runion, T. C.
Object Type: Report
System: The UNT Digital Library
Thermal Conductivity of Graphite (open access)

Thermal Conductivity of Graphite

Technical report outlining the differences in conductivity of AGOT graphite and AGHT graphite.
Date: November 28, 1949
Creator: Garth, R. C. & Sailor, V. L.
Object Type: Report
System: The UNT Digital Library
Reactor Operations Division Monthly Report; November 1951 (open access)

Reactor Operations Division Monthly Report; November 1951

Technical report outlining the downtime given to the Brookhaven National Laboratory nuclear reactor in November compared to previous months.
Date: November 1951
Creator: Powell, R. W.
Object Type: Report
System: The UNT Digital Library
Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data (open access)

Criticality Calculations for Hydrogen Moderated Reactors From Microscopic Data

From abstract: "The probability for a fission neutron to escape fast leakage from bare, hydrogen moderated reactors is calculated by a method utilizing only the microscopic cross section of the materials. These results can be employed to determine the effectiveness of other substances in preventing fast neutron leakage. These calculations are carried out for aluminum and iron."
Date: November 29, 1951
Creator: Shapiro, Mathew; Preiser, Stanley & Young, Gale
Object Type: Report
System: The UNT Digital Library
NURE Aerial Gamma Ray and Magnetic Reconnaissance Survey, Thorpe Area, Volume 1 - Narrative Report: Newark (NK 18-11) Quadrangle (open access)

NURE Aerial Gamma Ray and Magnetic Reconnaissance Survey, Thorpe Area, Volume 1 - Narrative Report: Newark (NK 18-11) Quadrangle

Final report documenting a high-sensitivity airborne radiometric and magnetic survey of the Newark quadrangles including the survey description, specifications, data processing methods, interpretation methods, and regional geologic review.
Date: November 1977
Creator: LKB Resources, Inc.
Object Type: Report
System: The UNT Digital Library
NURE Aerial Gamma Ray and Magnetic Reconnaissance Survey, Thorpe Area, Volume 2: Newark (NK 18-11) Quadrangle (open access)

NURE Aerial Gamma Ray and Magnetic Reconnaissance Survey, Thorpe Area, Volume 2: Newark (NK 18-11) Quadrangle

Second volume of a report documenting a high-sensitivity airborne radiometric and magnetic survey of the Newark quadrangle including maps documenting geophysical and geochemical data, as well as magnetic, ancillary and radiometric data.
Date: November 1977
Creator: LKB Resources, Inc.
Object Type: Report
System: The UNT Digital Library
Investigations in Automated Activation Analysis (open access)

Investigations in Automated Activation Analysis

Introduction: The Texas A. and M. Activation Analysis Research Laboratory has been studying the basic technology of activation analysis and its applications since 1958, under the spondorship of the Division of Isotopes Development, U. S. Atomic Energy Commission, and more recently, the National Aeronautics and Space Administration. The information presented in this report summarizes the progress which has been made in these efforts during the period from May 1, 1961, to October 31, 1962.
Date: November 1, 1962
Creator: Fite, Lloyd E.; Wainerdi, Richard E.; Steele, Edgar L.; Anderson, James; Drew, Dan; Forehand, Jim et al.
Object Type: Report
System: The UNT Digital Library