Resource Type

Experimental Determination of Contact Conductance for Some Stainless Steel Contacts (open access)

Experimental Determination of Contact Conductance for Some Stainless Steel Contacts

"Contact conductances for three semi-smooth and rough stainless steel contacts involving six steels are determined. The procedure and equipment used are fully described, and the results are given. Graphs display thermal conductance and conductivity versus pressure and temperature."
Date: July 1962
Creator: Adamantiades, Achilles
Object Type: Report
System: The UNT Digital Library
Basic and Applied Radiotracer Studies Annual Report: 1962 (open access)

Basic and Applied Radiotracer Studies Annual Report: 1962

Introduction: The primary objective of the work of this report was research and development leading to large-scale applications of low level isotope tracer technology.
Date: June 1962
Creator: Aebersold, Paul C. & Bizzell, Oscar M.
Object Type: Report
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962 (open access)

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
Date: August 17, 1962
Creator: Aerojet-General Corporation
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System

Final design for the 30 megawatt intermediate heat exchanger and steam generator.
Date: January 31, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis

Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.
Date: February 28, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Date: May 15, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator (open access)

Test Program for 30 Megawatt Prototype Sodium Intermediate Heat Exchanger and Steam Generator

The designer's concept of a test program for the 30-Mw prototype intermediate heat exchanger and steam generator designed and fabricated as part of the Sodium Components Development Program is presented. The performance data will serve to verify the thermal design, or allow application of improved techniques to future designs, give an improved basis for stress analysis in design of future units, and demonstrate the capability and limitations of the units in relation to the performance specifications for which they were designed. Welding techniques for type 316 stainless steel are described. The specifications and operating conditions of the units are given along with instrumentation drawings showing test equipment design and arrangement.
Date: September 14, 1962
Creator: Alco Products (Firm).
Object Type: Report
System: The UNT Digital Library
Plutonium Recycle Critical Facility: Final Safeguards Analysis (open access)

Plutonium Recycle Critical Facility: Final Safeguards Analysis

Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Date: February 1962
Creator: Anderson, J. K. & Winegardner, W. K.
Object Type: Report
System: The UNT Digital Library
Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions (open access)

Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions

Abstract: The MSAR corrosion test loop was used to study the effect of VKE-shaped crevices on the corrosion resistance of Zircaloy under boiling heat-transfer condtions in both ammoniated and lithiated water at pH 10.5.
Date: April 1962
Creator: Anderson, W. Kermit & McGoff, M. J.
Object Type: Report
System: The UNT Digital Library
The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium (open access)

The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium

From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it has been possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results are consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desoption of the adsorbed hydrogen. At very high temperatures the remaining carbon atoms are removed, presumably by evaporation."
Date: April 7, 1962
Creator: Arthur, John R., Jr. & Hansen, Robert S.
Object Type: Report
System: The UNT Digital Library
Conceptual Design Study of a Mobile Gamma Irradiator for Fruit Produce (open access)

Conceptual Design Study of a Mobile Gamma Irradiator for Fruit Produce

From introduction: This report covers the results of a study of a mobile irradiator for fruit grown in California.
Date: May 31, 1962
Creator: Associated Nucleonics (Garden City, N.Y.)
Object Type: Report
System: The UNT Digital Library
Disposition of Radiation Products and Energy Transfer in Radiobiological Processes (open access)

Disposition of Radiation Products and Energy Transfer in Radiobiological Processes

Technical report outlining the nature and effects of energy loss and radiation in biological materials during radiobiological processes.
Date: March 28, 1962
Creator: Augenstine, L. G.
Object Type: Report
System: The UNT Digital Library
A Versatile Bubble-Chamber Track Measuring Stage (open access)

A Versatile Bubble-Chamber Track Measuring Stage

Technical report describing a bubble chamber film track measuring stage designed for maximum versatility that was build at Brookhaven National Laboratory. The report includes photographs and diagrams of the device.
Date: March 1962
Creator: Ayer, Frederick, II & Bolze, Ernest M.
Object Type: Report
System: The UNT Digital Library
A Bubble Chamber Track-Centering Device with Digitized Output (open access)

A Bubble Chamber Track-Centering Device with Digitized Output

Technical report describing "A means for automatically determining the coordinates of a point at the center of a bubble chamber track." from the abstract.
Date: March 1962
Creator: Ayer, Frederick.; Pickup, Eric.; Rappe, Edwin F. & Wall, Gaylord.
Object Type: Report
System: The UNT Digital Library
Consolidated Nuclear Steam Generator for Merchant Ship Application: A Conceptual Design (open access)

Consolidated Nuclear Steam Generator for Merchant Ship Application: A Conceptual Design

Report concerning the economic feasibility of pressurized water reactors for use aboard merchant ships. This includes conceptual designs and work remaining for the future of a Pressurized Water Reactor.
Date: August 1962
Creator: Babcock & Wilcox Company
Object Type: Report
System: The UNT Digital Library
Preliminary Hazards Summary Report:  Babcock & Wilcox Test Reactor (open access)

Preliminary Hazards Summary Report: Babcock & Wilcox Test Reactor

This preliminary Hazards Summary Report presents to the Atomic Energy Commission (AEC), Division of Licensing and Regulation, a description of the Nuclear Development Center, the characteristics of the proposed site, and an evaluation of the potential hazards associated with operating the test reactor at this location.
Date: July 1962
Creator: Babcock & Wilcox Company
Object Type: Report
System: The UNT Digital Library
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code (open access)

The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code

Abstract: FAIM is a general multigroup, one-dimensional diffusion equation code programmed in FORTRAN language for the IBM 7090 computer.
Date: April 15, 1962
Creator: Baller, D. C.
Object Type: Report
System: The UNT Digital Library
͟v͟ic-Dioximes as Analytical Reagents (open access)

͟v͟ic-Dioximes as Analytical Reagents

This technical report discusses the synthesis of vic-dioximes, the analysis of vic-dioximes, the structure of vic-dioximes, the structure of metal(II)-vic-dioxime complexes, and analytical applications of this research. The report includes tables and figures that accompany the report's contents and findings.
Date: March 19, 1962
Creator: Banks, Charles V.
Object Type: Report
System: The UNT Digital Library
Stability Constants and Intrinsic Solubility of Several Nickel(II)-vic-Dioxime Complexes (open access)

Stability Constants and Intrinsic Solubility of Several Nickel(II)-vic-Dioxime Complexes

This technical report discusses processes to study the stability constants and intrinsic solubility of several Nickel(II)-vic-Dioxime complexes.
Date: March 19, 1962
Creator: Banks, Charles V. & Anderson, Samuel
Object Type: Report
System: The UNT Digital Library
Economic Factors of MFP Thermoelectric Generators (open access)

Economic Factors of MFP Thermoelectric Generators

"Mixed Fission Products (MFP) for use as a heat source for thermoelectric generators will become increasingly available in the coming years. The Atomic Energy Commission sponsored program on solidification of nuclear wastes is now entering the hot-bench scale test phase. During this phase approximately 5000 thermal watts of two year old MFP could be produced monthly. Two different types of hot calcination pilot plants are planned for installation at the Hanford National Laboratories in the 1964 to 1966 time period. Each of these plants should be able to produce 160,000 thermal watts of two year MFP and 16,000 thermal watts of ten year MFP on a monthly basis. A full scale plant for a 15,000 Mw(e) nuclear economy is estimated to produce four to five times as much MFP as either of the pilot plants. Costs will be dependent upon AEC policy in effect at the time the plant is operating."
Date: June 1962
Creator: Barmat, N.
Object Type: Report
System: The UNT Digital Library
N.S. Savannah Safety Assessment: Summary Report of Volumes 1 through 5 (open access)

N.S. Savannah Safety Assessment: Summary Report of Volumes 1 through 5

From title page: This report has been prepared at the request of the Government of Germany for consideration under their Atomic Energy Act for a license for the operation of the N.S. Savannah in German ports.
Date: December 1962
Creator: Barrett, James M. & Carrico, Paul E.
Object Type: Report
System: The UNT Digital Library
The Scandium-Yttrium and Scandium-Zirconium System (open access)

The Scandium-Yttrium and Scandium-Zirconium System

Technical report. From Abstract : "The scandium-yttrium and scandium-zirconium were studied by thermal and x-ray methods. Both systems are characterized by complete solid solubility in the low temperature hexagonal form and in the high temperature bcc form. In the Sc-Y system, there is a minimum in the solidus at 50 at. pct and 1365°C, while the solidus in the Sc-Zr system follows a nearly straight line relationship between the melting point of scandium and zirconium. There is a minimum in the temperature of transition from hexagonal to bcc in the Sc-Y system at 43 at. pct Y and 1175°C; while the temperature of transition is raised in the Sc-Zr system to a maximum of 1415°C at 30 at. pct Zr."
Date: October 26, 1962
Creator: Beaudry, B. J. & Daane, A. H.
Object Type: Report
System: The UNT Digital Library
Self-Diffusion in Polycrystalline Yttrium Oxide (open access)

Self-Diffusion in Polycrystalline Yttrium Oxide

From abstract: "The self-diffusion coefficient of yttrium in yttrium oxide has been determined for polycrystalline Y2O3 in the temperature range 1400 to 1800°C. Radioactive Y-91 was deposited on sintered specimens of 94 to 97% theoretical density. The specimens were annealed under vacuum and sectioned. The following equation describes the temperature dependence of the diffusion coefficient over the range studied: D = 2.41 x 10[^]-4 exp (-43,900/RT) cm[^]2/sec."
Date: 1962
Creator: Berard, M. F. (Michael F.), 1938- & Wilder, D. R.
Object Type: Report
System: The UNT Digital Library
A Needle in a Haystack (open access)

A Needle in a Haystack

Abstract: "Production of [rho]'s and [omega]'s in [pi]- + p and p + [letter p with a bar over it] interactions is discussed. The [rho] is presumably a J = 1-, 1 = 1 state and thus can decay into 2[pi]'s via a strong coupling. The [omega] is probably J = 1-, 1 = 0 which can also decay into 2[pi]'s via electromagnetic coupling. A theoretical description of this situation is presented in terms of coupled time-dependent Schroedinger equations which mix [rho] and [omega] states that are assumed to be isotopically pure at the time of production. The interference between the two resonances was found to have the effect of extending the 2[pi] spectrum toward the [omega] mass."
Date: May 25, 1962
Creator: Bernstein, J. & Feinberg, Gerald, 1933-1992
Object Type: Report
System: The UNT Digital Library