Resource Type

The Design and Performance of Levitation Melting Coils (open access)

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
Object Type: Report
System: The UNT Digital Library
The Inference of Adsorption from Differential Double Layer Capacitance Measurements (open access)

The Inference of Adsorption from Differential Double Layer Capacitance Measurements

From Abstract : "Dependence of boundary tension and capacitance at the mercury-aqueous 0.1 N HClO4 interface on polarization and organic solute concentration were determined for the colutes n-amyl alcohol and phenol. ... An earlier treatment proposed by this Laboratory based on a (non-thermodynamic) assumption of linear variation of surface charge density with coverage appears adequately justified for inference of fractional surface coverages near the electrocapillary maximum, but must be considered approximate for evaluation of molar area at full coverage in cases where linear variation of charge with coverage has not been demonstrated."
Date: April 26, 1963
Creator: Hansen, Robert S.; Kelsh, Dennis J. & Grantham, D. H.
Object Type: Report
System: The UNT Digital Library
The Thermal Expansion of Thirteen Tungsten Carbide Cermets from 68 to 1800 F (open access)

The Thermal Expansion of Thirteen Tungsten Carbide Cermets from 68 to 1800 F

The linear thermal expansion of thirteen tungsten carbide cermets with cobalt binder was investigated experimentally over the temperature range from 68 to 1800 F. Cobalt contents varied from 2.5 to 60 per cent. Several compositions included additions of mixed carbides of titanium, tantalum, and columbium. The experimentally observed coefficients of thermal expansion for the various compositions were compared with coefficients analytically computed from the coefficients for the constituents. Three such analytical methods were evaluated. In one method, the coefficient of expansion of the mixture was computed by volume fractions and in a second method by weight fractions. In the third method, the computation accounted for the stresses set up in the mixture by the difference in thermal expansion of the carbide skeleton and the cobalt binder. The expansions of all these cermets agreed with the values computed by weight fractions or by the stress method within 12 per cent, and by volume fractions within 28 per cent. The cermets containing less than one per cent mixed carbides agreed with the expansion computed either by weight fractions or by stress within 8 per cent, the cermets containing more than five per cent mixed carbides agreed with values computed by volume fractions …
Date: April 26, 1963
Creator: Harrington, L. C. & Rowe, G. H.
Object Type: Report
System: The UNT Digital Library
Fast Reactor Fuel Cycle Costs and Temperature Coefficients of Reactivity for PuO2-SS and PuO2-UO2 (open access)

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.
Object Type: Report
System: The UNT Digital Library
Measurement of Thermal Properties by the Arc Image Furnace (open access)

Measurement of Thermal Properties by the Arc Image Furnace

Technical report. From Abstract : "A number of imaging furnace systems and sources are discussed with emphasis on the carbon arc image furnace. Several potential applications of the carbon arc image furnace in high temperature research are described and a new method of heat capacity determination is discussed."
Date: April 16, 1963
Creator: McMahon, W. R. & Wilder, D. R.
Object Type: Report
System: The UNT Digital Library
High Performance UO2 Program Quarterly Progress Report No.8 : January-March 1963 (open access)

High Performance UO2 Program Quarterly Progress Report No.8 : January-March 1963

Work performed during the quarter is summarized by direct measurement of fission gas pressure, loop operations, performance of UO2 fuel.
Date: April 15, 1963
Creator: Weidenbaum, B.
Object Type: Report
System: The UNT Digital Library
High Power Density Development Project: Twelfth Quarterly Progress Report, January-March 1963 (open access)

High Power Density Development Project: Twelfth Quarterly Progress Report, January-March 1963

From introduction: "Development of nuclear reactor cores having high power density, long fuel life, and low fabrication costs is the objective of this program sponsored by the AEC."
Date: April 15, 1963
Creator: Holland, L. K.
Object Type: Report
System: The UNT Digital Library
Influence of a Sector Ground Screen on the Field of a Vertical Antenna (open access)

Influence of a Sector Ground Screen on the Field of a Vertical Antenna

Report show the field of a short vertical antenna on a homogeneous ground is modified by the presence of a metallic screen. The screen is taken in the form of a circular disk and a concentric sector. The modification of the field is expressed in the form of surface integrals over the disk and the sector. Extensive numerical results for these basic integrals are given and a number of applications are illustrated.
Date: April 15, 1963
Creator: Wait, James R. & Walters, Lillie C.
Object Type: Report
System: The UNT Digital Library
Reactor Development Program Progress Report: March 1963 (open access)

Reactor Development Program Progress Report: March 1963

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: April 15, 1963
Creator: Adams, R. M. & Glassner, A.
Object Type: Report
System: The UNT Digital Library
Transition Boiling Heat Transfer Program; First Quarterly Progress Report, February - March 1963 (open access)

Transition Boiling Heat Transfer Program; First Quarterly Progress Report, February - March 1963

Introduction: The Transition Boiling Heat Transfer Program is sponsored jointly by the USAEC and Euroatom and is being conducted by the General Electric Company. The work commenced on this program February 11, 1963. The objective of this program is to perform basic investigation and measurement of the transition boiling regime in high pressure bulk boiling water flows, with particular emphasis i the high range of steam qualities.
Date: April 15, 1963
Creator: Tippets, F. E.
Object Type: Report
System: The UNT Digital Library
A Versatile Spectrometer Magnet Power Supply (open access)

A Versatile Spectrometer Magnet Power Supply

Early results from actual laboratory operation of a more versatile magnet supply.
Date: April 15, 1963
Creator: Groppe, W. A.
Object Type: Report
System: The UNT Digital Library
Design and Test of a Diaphragm Pump for Liquid Metals (open access)

Design and Test of a Diaphragm Pump for Liquid Metals

Technical report. From Abstract : "Details are provided on the construction and operation of a two-stage diaphragm pump successfully used for the first time in liquid metal service. From the results of 5,376 hr. test of the pump it was concluded that it is well suited to the pumping of liquid metals at low flow rates where pulsating flow can be tolerated and also where remote operation is required. Operating temperatures and pressures are limited only by the availability of suitable materials of construction."
Date: April 12, 1963
Creator: Westerheide, D. E. & Clifford, J. C.
Object Type: Report
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.
Object Type: Report
System: The UNT Digital Library
Army Reactors Program Annual Progress Report: 1962 (open access)

Army Reactors Program Annual Progress Report: 1962

Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Date: April 10, 1963
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Errata for ANL-6628: Automatic Foil Activity Counting Facility and Data-Reduction Program (open access)

Errata for ANL-6628: Automatic Foil Activity Counting Facility and Data-Reduction Program

Errata sheet listing corrections to three pages of a report that describes a transistorized automatic counting and recording system built for the determination of foil-activation data.
Date: April 8, 1963
Creator: Glassner, Alvin
Object Type: Text
System: The UNT Digital Library
Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: January 1 - March 31, 1963. (open access)

Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: January 1 - March 31, 1963.

A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. All program efforts have been temporarily deferred except for those associated with the irradiation of the program fuel element in the VBWR. The program fuel element was exposed to a burnup of 465 MWD/T during the quarter which brings the total to 2334 MWD/T. On the basis of the computed isotopic composition, the burnup obtained was 1450 MWD/T.
Date: April 8, 1963
Creator: Robkin, M. A.
Object Type: Report
System: The UNT Digital Library
Fuel Cycle Program Progress Report: Eleventh Quarter, January-March 1963 (open access)

Fuel Cycle Program Progress Report: Eleventh Quarter, January-March 1963

Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
Date: April 5, 1963
Creator: Howard, C. L.
Object Type: Report
System: The UNT Digital Library
Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962 (open access)

Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962

Report documenting research and developments made by the Maritime Reactor Program of the Oak Ridge National Laboratory.
Date: April 4, 1963
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
High Purity Calcium (open access)

High Purity Calcium

Technical report. From Introduction : "For more than a century, methods employed in preparing calcium were based largely on electrowinning and the most successful were based on [Sir Humphrey] Davy's process. ... In general, the metal was of adequate quality for the industrial applications of the time, and although by 1940 some strides had been made in the purification of calcium, interests in the better grades of the metal were limited essentially to experimental work of academic concern."
Date: April 3, 1963
Creator: Wilhelm, H. A. & Carlson, O. N.
Object Type: Report
System: The UNT Digital Library
A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations (open access)

A 1620 FORTRAN Programme for the Calculation of Bragg Angles for use in Powder X-Ray Diffraction Investigations

An IBM 1620 program is described that calculates the Bragg angles for cubic, hexagonal, and tetragonal crystal systems for use with powder x-ray diffraction techniques. Allowance is made for absent reflections in the case of face- and body-centered cubic and close-packed hexagonal materials.
Date: April 1963
Creator: Walker, D. G.
Object Type: Report
System: The UNT Digital Library
A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method (open access)

A 1620 FORTRAN Programme for the Refinement of Lattice Parameters by a Modified Least Squares Method

An I.B.M. 1620 programme is described which calculates refined lattice parameters from X-ray diffraction data according to Hess' Method. The programme may be used for cubic, hexagonal, and tetragonal systems and three systematic error functions are included. The output includes the refined parameters their stand errors, and the misfit of the data at each experimental point.
Date: April 1963
Creator: Walker, D. G.
Object Type: Report
System: The UNT Digital Library
An Automatic Monitor for As76 Concentrations in Reactor Cooling Water (open access)

An Automatic Monitor for As76 Concentrations in Reactor Cooling Water

Report that describes the development, design, and operation of a prototype instrument meant to monitor the As76 concentration in reactor cooling water streams.
Date: April 1963
Creator: Rieck, H. G. 1922-
Object Type: Report
System: The UNT Digital Library
A Cryostat for Temperature Control in the Range from Ambient to - 150 degrees C (open access)

A Cryostat for Temperature Control in the Range from Ambient to - 150 degrees C

This note describes a simple cryostatic device, which, by utilizing the latent heat of vaporization of liquid nitrogen, enables accurate control of temperature between ambient and - 150 degrees C. The advantages of this cryostat over other models known are simplicity of design and operation, ability to operate accurately from ambient to - 150 degrees C, economy, and large working space.
Date: April 1963
Creator: Roman, D.
Object Type: Report
System: The UNT Digital Library
Cumulative Bibliography of Literature Examine by the Radiation Shielding Information Center (open access)

Cumulative Bibliography of Literature Examine by the Radiation Shielding Information Center

This bibliography represents the first cumulative edit of the literature examined by the Radiation Shielding Information Center recently established at the Oak Ridge National Laboratory. Its two major sections consist of a list of documents by subject category and of an author index. The document list covers nine major subjects with a total of 118 categories; however, literature specimens have not yet been entered for all categories. If a document applies to more than one category, it is listed under each. The author index includes cross references to the categories under which each author's publications appear. Preceding the bibliography is a list of the subject categories, their corresponding category numbers and the pages on which they appear in the bibliography,
Date: April 1963
Creator: Radiation Shielding Information Center (U.S.)
Object Type: Report
System: The UNT Digital Library