Resource Type

Liquid Metal Fast Breeder Reactor Design Study (open access)

Liquid Metal Fast Breeder Reactor Design Study

From introduction: "The primary objective of the present study was to develop a conceptual design of a large sodium cooled fast breeder reactor of a nominal electrical rating of 1000 Mw operating on the uranium-plutonium cycle."
Date: January 1964
Creator: unknown
System: The UNT Digital Library
SL-1 Annual Operating Report: February, 1960-January 3, [1961] (open access)

SL-1 Annual Operating Report: February, 1960-January 3, [1961]

The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
Date: June 15, 1961
Creator: unknown
System: The UNT Digital Library
Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions (open access)

Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions

Theoretical investigation on the nature of ion exchange of acidified uranyl sulfate solutions with Dowex 21K, a strong base ion exchange resin.
Date: September 28, 1962
Creator: Stein, P. E.
System: The UNT Digital Library
Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant (open access)

Effects of Major Parameters on Cycle Efficiency and Cost for a Gas-Cooled Reactor Turbine Power Plant

Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.
Date: October 5, 1962
Creator: Miskell, R. V.
System: The UNT Digital Library
Automatic Mass Spectrometer for Isotopic Analysis of Lithium (open access)

Automatic Mass Spectrometer for Isotopic Analysis of Lithium

Report discussing an improvement program on lithium mass spectrometers.
Date: March 15, 1962
Creator: McBryde, W. T. & Gammon, E. F.
System: The UNT Digital Library
A Computer Program for Determining First-Collision Neutron Doses (open access)

A Computer Program for Determining First-Collision Neutron Doses

Data processing program written to compute the neutron dose received by individuals exposed in a nuclear excursion.
Date: May 21, 1962
Creator: McMurray, C. S.
System: The UNT Digital Library
The Application of Data Processing Techniques to a Maintenance Work Control Program (open access)

The Application of Data Processing Techniques to a Maintenance Work Control Program

Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division.
Date: December 18, 1963
Creator: Westbrook, J. D.
System: The UNT Digital Library
The Cold Pressing of Sinterable UO₂ (open access)

The Cold Pressing of Sinterable UO₂

The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date: March 27, 1961
Creator: Levey, R. P., Jr.
System: The UNT Digital Library
Transistorized Pulse Counting Equipment (open access)

Transistorized Pulse Counting Equipment

This instrument was designed primarily to meet the need for radiation monitoring equipment in chemical process areas where corrosive vapors exist.
Date: July 26, 1960
Creator: Henry, John J.
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.
System: The UNT Digital Library
An Investigation of a "Dynamic" Theory for Mass Transfer (open access)

An Investigation of a "Dynamic" Theory for Mass Transfer

A new theory is proposed to evaluate individual mass-transfer coefficients without actual experiment.
Date: July 18, 1960
Creator: Schappel, Richard B.
System: The UNT Digital Library
A Continuous Water Monitor for Detecting PPM Quantities of Alkali Metals (open access)

A Continuous Water Monitor for Detecting PPM Quantities of Alkali Metals

Abstract: "This report describes a flame photometric system which continuously monitors a process water stream for ppm quantities of alkali metals, and automatically diverts the stream when the contamination exceeds a pre-determined level."
Date: June 20, 1955
Creator: Been, Julian F.
System: The UNT Digital Library
Shipboard Cobalt-60 Radiopasteurizer for Marine Products (open access)

Shipboard Cobalt-60 Radiopasteurizer for Marine Products

Report issued by the Brookhaven National Laboratory discussing the shipboard cobalt-60 irradiator. As stated in the introduction, "this report discusses the conceptual design of a cobalt-60 shipboard irradiator for use to improve the keeping quality of fish landed aboard commercial fishing trawlers operating out of ports along the eastern seaboard of the commercial United States" (p. 1). This report includes tables, and illustrations.
Date: June 30, 1963
Creator: Manowitz, B.; Kuhl, A. O.; Galanter, L.; Armel, J.; Black, K. M.; Klaassen, W. J. et al.
System: The UNT Digital Library
Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies (open access)

Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies

Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
Date: 1964
Creator: Vogel, G. J.; Carls, E. L. & Mecham, W. J.
System: The UNT Digital Library
Potential Applications of Nuclear Energy for Process and Space Heat in the United States (open access)

Potential Applications of Nuclear Energy for Process and Space Heat in the United States

A survey and analysis of the potential opportunity for the use of nuclear reactors to satisfy process and space heat requirements in the continental United States and Alaska has been completed. The greatest emphasis has been devoted to manufacturing industries that utilize large quantities of process heat.
Date: October 1958
Creator: Geiringer, Paul Ludwig & Goodfriend, Morton J.
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
System: The UNT Digital Library
The Design Study of Fluid Engine Power Systems (open access)

The Design Study of Fluid Engine Power Systems

From abstract: This report presents information generated during a six month feasibility study of an engine which uses a supercritical working fluid as the secondary portion of nuclear powered electric generating system.
Date: April 12, 1963
Creator: Baker, C. H.; Hunter, T. A.; Pauliukonis, R. S. & Pradhan, A. V.
System: The UNT Digital Library
A Nuclear Reactor System for Generating Power and Supplying Steam to a Water Desalination Plant in the Florida Keys (open access)

A Nuclear Reactor System for Generating Power and Supplying Steam to a Water Desalination Plant in the Florida Keys

From foreword: The results of an engineering study directed toward the evaluation and selection of a nuclear reactor system designed to produce electricity and furnish steam to a water desalination plant in the Florida Keys are given in this report.
Date: March 1964
Creator: Burns and Roe
System: The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin (open access)

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."
Date: September 29, 1952
Creator: Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
System: The UNT Digital Library
Mechanical Properties of Zirconium and Zirconium-Uranium Alloys Containing Tin (open access)

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."
Date: September 29, 1952
Creator: Schwope, A. D.; Muehlenkamp, G. T. & Chubb, Walston
System: The UNT Digital Library
The Ductility of Brazed Stainless Steel Joints (open access)

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."
Date: July 8, 1953
Creator: Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
System: The UNT Digital Library
The Effect of Copper, Nickel, Iron, and Chromium on the Tensile Properties of Preferentially Oriented Beryllium Sheet (open access)

The Effect of Copper, Nickel, Iron, and Chromium on the Tensile Properties of Preferentially Oriented Beryllium Sheet

From abstract: The planes and modes of fracture as a result of the mixture of beryllium and other elements were investigated.
Date: February 14, 1958
Creator: Yans, F. M.; Donaldson, A. D. & Kaufmann, A. R.
System: The UNT Digital Library
Fundamental and Applied Research and Development in Metallurgy: Conceptual Design of a U-233 Fuel Refabrication Plant (open access)

Fundamental and Applied Research and Development in Metallurgy: Conceptual Design of a U-233 Fuel Refabrication Plant

From abstract: A preliminary study has been made of a direct access, streamlined process for the rapid fabrication of fuel using uranium-233.
Date: July 30, 1962
Creator: Nowak, W. B. & Wessling, B. W.
System: The UNT Digital Library
Feed Materials Production Center Summary Technical Report: January 1, 1963-March 31, 1963 (open access)

Feed Materials Production Center Summary Technical Report: January 1, 1963-March 31, 1963

This is a summary report of various technical projects relating to uranium.
Date: May 10, 1963
Creator: unknown
System: The UNT Digital Library