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Advanced Test Reactor: Final Shielding Design Report
From abstract: "This report has been prepared as a design reference document describing the calculation methods and engineering results for shielding analysis work done during the design of the Advanced Test Reactor."
Date:
December 1963
Creator:
Howard, J. O. & Jacks, G. M.
System:
The UNT Digital Library
Analysis of Failure of Type 304 Stainless Steel Clad Swaged Powder Fuel Assembly
From introduction: "The purpose of this report is to describe the observations made during the post-irradiation examination of HPD-2S, and to discuss possible modes of failure.
Date:
October 3, 1963
Creator:
Lees, E. A.
System:
The UNT Digital Library
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
Cubic Spline, a Curve Fitting Routine
A method of mathematically fitting a curve through a given ordered set of points has been developed and programmed in fortran computer language.
Date:
1963
Creator:
Fowler, A. H.
System:
The UNT Digital Library
Design and Economic Evaluation of Fixed Blankets for Fast Reactors
Report evaluating the design characteristics and limitations of fixed blankets for breeder reactors. This also includes economic considerations for each tested blanket.
Date:
August 30, 1963
Creator:
Klickman, A. E.; Ball, G. L.; Edwards, J. J.; Jens, W. H.; Segal, B. M.; Stanford, R. E. L. et al.
System:
The UNT Digital Library
The Design and Performance of Levitation Melting Coils
The purpose of this study was to provide a means for evaluating the various parameters involved in the design and performance of levitation coils.
Date:
April 26, 1963
Creator:
Hulsey, William Jewell
System:
The UNT Digital Library
The Design of a Dynamic Corrosion and Chemical Control Test Loop and Preliminary Out-of-Pile Test Results
From abstract: "This report describes the overall loop design and the means by which this design was developed. These include critical facility measurements, analog computer calculations, hydraulic and heat transfer computations, and the construction and operation of an out-of-pile mock-up loop to determine the dynamic characteristics of the loop."
Date:
July 12, 1963
Creator:
Zelezny, W. F.
System:
The UNT Digital Library
EDP Procedures in Technical Library Operations
Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
Date:
July 30, 1963
Creator:
Griffin, Hillis L.
System:
The UNT Digital Library
Evaluation of Diethers as Uranium Extractants
Report on the determination of several physical properties, pertinent to uranium extraction, for a number of ethers and related compounds.
Date:
January 14, 1963
Creator:
Googin, J. M.; Harper, W. L.; Phillips, L. R. & Postma, Fred W.
System:
The UNT Digital Library
Evaluation of Failed Hot Gas Isostatic Pressed Fuel Rods
From introduction: "Evaluations to determine cause of fuel rods breakage following irradiation."
Date:
March 20, 1963
Creator:
Baroch, C. J. & Boyer, C. B.
System:
The UNT Digital Library
Evaluation of Radiation Stabilizers for Terphenyl by High-Temperature Electron Irradiation
From summary: "Experiments to determine effectiveness of additives to reduce radiolytic damage to a mixture of isometric terphenyls in which 93 separate compounds were evaluated."
Date:
January 23, 1963
Creator:
Hartzfeld, H. A. & Regier, R. B.
System:
The UNT Digital Library
Fast Ceramic Reactor Development Program: Experimental Studies of Sodium Logging in Fast Ceramic Reactor Fuels
From abstract: "The experimental determination of the effects of sodium ingress on high-performance oxide fuels is described. Capsule design, fabrication, irradiation, examination, and analysis are described in detail."
Date:
September 1963
Creator:
O'Neill, G. L.; Novak, P. E.; Johnson, M. L. & Baily, W. E.
System:
The UNT Digital Library
Fast Reactor Fuel Cycle Costs and Temperature Coefficients of Reactivity for PuO2-SS and PuO2-UO2
Report comparing the fuel cycle costs and temperature coefficients of reactivity for PuO2-UO2 fuel in multiple megawatt reactors.
Date:
April 25, 1963
Creator:
Edwards, J. J.; Fischer, E. A.; Jens, W. H.; Nims, J. B.; Palmer, R. G.; Shoudy, A. A. et al.
System:
The UNT Digital Library
Fundamentals in the Operation of Nuclear Test Reactors: Volume 2, Materials Testing Reactor Design and Operation
Second volume of reports on the operation of nuclear test reactors. It includes six chapters: engineering description fo the materials testing reactor, reactor control components and instrumentation, reactor control circuitry, reactor operation, reactor shutdown and tank work, and supplemental facilities at the materials testing reactor.
Date:
October 1963
Creator:
Phillips Petroleum Company
System:
The UNT Digital Library
High-Temperature Irradiation of UOâ‚‚-BeO Bodies
From introduction: "Irradiation experiment performed to simulate burnup data under close to reactor temperatures."
Date:
January 1963
Creator:
Titus, G. W. & Saling, J. H.
System:
The UNT Digital Library
Hydrology of Waste Disposal, National Reactor Testing Station, Idaho: Annual Progress Report, 1962
Report describing investigations to determine the effect of underground disposal of liquid radioactive waste upon the regional groundwater resources.
Date:
April 1963
Creator:
unknown
System:
The UNT Digital Library
Materials for Superheated Fuel Sheaths: Relative Performance of Alloys in Superheated Steam Environments
From abstract: "Study of radiation effects upon the tensile properties of the alloys, corrosion behavior in the absence and presence of stress, effect of prolonged, high temperature exposures upon structure sensitive properties of the alloys, and physical metallurgical changes as a function of exposure in a superheat environment.
Date:
July 1963
Creator:
Comprelli, F. A.; MacMillan, D. F. & Spalaris, C. N.
System:
The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 5, Fuel Element Rupture Testing Facility Analysis
This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.
Date:
May 1963
Creator:
Hanthorn, H. E.
System:
The UNT Digital Library
Pressure Intensification Provided by External Pressure on a Cylinder Composed of Four Anvils
Results of experimental investigation for improving intensification and to reduce stress concentrations for anvil redesign.
Date:
December 6, 1963
Creator:
Huddleston, R. L.
System:
The UNT Digital Library
Quarterly Progress Report Metallurgy Research Operation: July, August, September, 1963
Quarterly progress report metallurgy research operation at Hanford Atomic Products Operation in Richland, Washington.
Date:
December 30, 1963
Creator:
unknown
System:
The UNT Digital Library
N-Reactor Operational Safety Review
Report describing a series of tests performed to review the safety procedures and systems of Hanford Laboratories' N-Reactor.
Date:
August 19, 1963
Creator:
Trumble, R. E.
System:
The UNT Digital Library
Research and Developement on Fabrication of Pin and Lid Detectors and the Dry Run Interface System, Final Report
Final report on research and development on fabrication of pin and lid detectors and the dry run interface system.
Date:
August 31, 1963
Creator:
Ziemba, F. P.; Katzenstein, H. S.; Zatzick, M. R. & Bernescut, R.
System:
The UNT Digital Library
Routine Testing and Calibration Procedures for Multichannel Pulse Analyzers and Gamma-Ray Spectrometers
Report describing the results of laboratory tests with procedures for calibration of equipment and performance requirements.
Date:
November 1, 1963
Creator:
Crouch, D. F. & Heath, R. L.
System:
The UNT Digital Library
Safety Analysis Report : Snaptran 2/10A-1 Safety Tests
From summary: "The report contains descriptions and discussions on nuclear safety testing."
Date:
January 28, 1963
Creator:
Waage, J. M.
System:
The UNT Digital Library