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The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System (open access)

The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System

Abstract: Electrical resistance measurements and metallography were employed in a study of the kinetics of the gamma to gamma prime transformation in the uranium-molybdenum system at 16 wt% molybdenum.
Date: December 31, 1961
Creator: Kramer, D. & Rhodes, C. G.
Object Type: Report
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1961 - December 1, 1961 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1961 - December 1, 1961

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: December 30, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Object Type: Report
System: The UNT Digital Library
Large-Scale Slurry-Circulation System, 300-SM (open access)

Large-Scale Slurry-Circulation System, 300-SM

Design philosophy, status of component development, operational procedures, and limitations of each section of the Oak Ridge large-scale, high-temperature, thoria slurry facility.
Date: December 21, 1961
Creator: Parsly, L. F., Jr.; Falkenberry, H. L.; Harley, P. H.; Miller, I. M. & Kenyon, V. L.
Object Type: Report
System: The UNT Digital Library
Reconnaissance for Uranium in the Chanaral-Taltal area, Provinces of Antofagasta and Atacama, Chile (open access)

Reconnaissance for Uranium in the Chanaral-Taltal area, Provinces of Antofagasta and Atacama, Chile

Abstract: In the Chañaral-Taltal area of northern Chile irregular replacement type iron deposits are especially well developed along a somewhat radioactive lithologic belt in andesite volcanic rocks and Cretaceous dioretic intrusions to the east of the Atacama fault, a prominent shear zone.
Date: December 1961
Creator: Bowes, William A.; Knowles, Paul H.; Moraga B., Aldo & C., Mario Serrano
Object Type: Report
System: The UNT Digital Library
Reconnaissance for Uranium in the San Pedro de Atacama and Laco areas, Province of Antofagasta, Chile (open access)

Reconnaissance for Uranium in the San Pedro de Atacama and Laco areas, Province of Antofagasta, Chile

Abstract: A reconnaissance for uranium in and a general geologic study of the San Pedro de Atacama and Laco areas of nothern Chile disclosed no significant radioactivity in the Laco area, but near San Pedro de Atacama slight anomalies were detected in limey silts of the San Pedro formation.
Date: December 1961
Creator: Knowles, Paul H.; Bowes, William A.; C., Mario Serrano & Moraga B., Aldo
Object Type: Report
System: The UNT Digital Library
Spectral Shift Control Reactor Design and Economic Study (open access)

Spectral Shift Control Reactor Design and Economic Study

Study of nuclear power plants incorporating the Spectral Shift Control Reactor (SSCR).
Date: December 1961
Creator: Mars, D. & Gans, D., Jr.
Object Type: Report
System: The UNT Digital Library
Status of the Application of Nuclear Reactors in the Process Industries: 1961 (open access)

Status of the Application of Nuclear Reactors in the Process Industries: 1961

From preface: This report is a detailed summary of the evaluation studies of civilian power reactor concepts. It is intended to present the current state of the use of nuclear reactors in process industries and current AEC program in this field.
Date: December 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Zircaloy Cladding Thickness Testers (open access)

Zircaloy Cladding Thickness Testers

Technical report. From Abstract : "A number of similar eddy current instruments were developed to measure the thickness of Zircaloy over uranium metal in the range of 5 to 25 mils, Zircaloy over UO2 in the range of 20 to 40 mils, and the wall thickness of Zircaloy tubes in the range of 20 to 40 mils. The instruments were designed for use with hand-held probes or with feeder-mounted probes to measure the inside and outside cladding thickness of tubular elements and the wall thickness of Zircaloy sheaths. The instruments have a sensitivity of 3 microamps per mil change in Zircaloy thickness and an accuracy of +/- mil."
Date: December 1961
Creator: Goodwin, Leslie E.
Object Type: Report
System: The UNT Digital Library
Alpha Particle Radiolysis of Anion Exchange Resins (open access)

Alpha Particle Radiolysis of Anion Exchange Resins

Technical report. From Abstract : "Irradiation of 'Dowex' 1, 'Permutit' S-1, and 'Permutit' SK anion exchange resins with alpha particles results in losses in ion exchange capacity and in 'apparent per cent crosslinkage'. The order of decreasing radiolytic stability for these properties in 'Permutit" SX > 'Permutit' S-1 > 'Dowex' 1."
Date: November 1961
Creator: Ahrens, Rolland W.
Object Type: Report
System: The UNT Digital Library
Analysis of Mixtures of Alcohols by Acylation (open access)

Analysis of Mixtures of Alcohols by Acylation

From abstract: "Recently a general chemical method for the analysis of mixtures of alcohols appeared, using pyridine catalyzed acetylation and second order kinetics to determine the amount of the faster reacting component. The use of 0.25M isobutyric anhydride in pyridine containing 0.0025M perchloric acid as catalyst promotes the rate of the reaction and diminishes the time necessary to perform an analysis. A mathematical treatment of the data and kinetic plot reduces the number of kinetic points to only four or five. The mixtures are primarily composed of isomers."
Date: November 1961
Creator: Fellows, William Dean & Fritz, James S. (James Sherwood), 1924-
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
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
Nuclear Superheat Quarterly Project Report: Sixth Quarter, October-December 1960 (open access)

Nuclear Superheat Quarterly Project Report: Sixth Quarter, October-December 1960

From introduction: "This is the sixth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: November 1961
Creator: Pennington, R. T.
Object Type: Report
System: The UNT Digital Library
The Post-Irradiation Examination of a PuOâ‚‚-UOâ‚‚ Fast Reactor Fuel (open access)

The Post-Irradiation Examination of a PuOâ‚‚-UOâ‚‚ Fast Reactor Fuel

From abstract: "Post-irradiation examination consisted of dimensional measurements, gamma scans, determination of fission gas release, visual examination of the fuel, measurement central voids, and metallographic examination of selected samples.
Date: November 1961
Creator: Gerhart, J. M.
Object Type: Report
System: The UNT Digital Library
Some methods of surface analysis for the prediction of thermal resistance of metal contacts (open access)

Some methods of surface analysis for the prediction of thermal resistance of metal contacts

"Equations for the heat-transfer coefficient existing at the interface of two metals in contact are discussed. The results of applying the equations (with a graphical determination of the geometric parameters) to an iron--aluminum contact are presented. A method is given for performing the graphical analysis by means of a general purpose analog computer. Data are included that were obtained by applying this method to Blanchard ground stainless steel surfaces in contact. Statistical analysis was applied to surfaces to determine the geometric properties of the contact as a function of root-mean-square roughness and method of surface preparation."
Date: November 1, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library
The Thermal Hydraulics Laboratory at Hanford (open access)

The Thermal Hydraulics Laboratory at Hanford

Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Date: November 1961
Creator: Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
Object Type: Report
System: The UNT Digital Library
Fifth Quarterly Progress Report on Fission Product Applications Using Gaseous Beta Sources (open access)

Fifth Quarterly Progress Report on Fission Product Applications Using Gaseous Beta Sources

"Rates of acetylene polymerization induced by Kr/sup 85/ in d-c fields were up to 15 times greater than those observed when no fields were imposed. Work to determine the relations between acetylene pressure, Kr/sup 85/ concentration, and the field intensity is continuing. In other activities, equipment is being designed to study the effects of megacycle electric fields on radioinduced chemical reactions."
Date: October 31, 1961
Creator: Graessley, William W. & Zufall, John W.
Object Type: Report
System: The UNT Digital Library
Final Contract Report for September 1, 1959 to August 31, 1960 . (open access)

Final Contract Report for September 1, 1959 to August 31, 1960 .

"As presented in the original proposal the project consisted essentially of three parts: Phase I, Development and refinement of a radiochemical flow counting technique for the study of kinetics of reactions in solution ; Phase II, The application of this technique to the detailed study of the mechanism of solvolysis of sulfonium salts in mixed solvents ; Phase II, The further application of this kinetic technique, as a longer term aim, to other reacting systems of biochemical or other interest. This report covers the work of the contractual period 1 Sept. 1959 to 31 Aug. 1960."
Date: October 31, 1961
Creator: Hyne, James B.; Abrell, J. W.; Gurst, J. E. & Jacobson, Ada L.
Object Type: Report
System: The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1961 (open access)

Health Physics Division Annual Progress Report, July 31, 1961

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date: October 31, 1961
Creator: Oak Ridge National Laboratory. Health Physics Division.
Object Type: Report
System: The UNT Digital Library
Synthesis of Semiconductor Materials by Radiation Induced Reactions (open access)

Synthesis of Semiconductor Materials by Radiation Induced Reactions

""Progress is reported on: design of a continuous flow system for the irradiation of silane using a Cos5 source; pile irradiation of silane samples at elevated temperatures; investigation of materials other than silane, including nonsilicon compounds as well as those containing the silyl group; modification of the existing vacuum system for handling larger quantities of silane as well as increasing the accuracy of the pressure measurements; and use of an electric discharge for the decomposition of silane. Studies were continued on the radiation- and thermalinduced decomposition of sikane at 325 and 350 deg C. A preliminary value of G= 33 was obtained for silane."
Date: October 31, 1961
Creator: {{{name}}} & Goldman, Richard
Object Type: Report
System: The UNT Digital Library
Synthesis of Semiconductor Materials by Radiation Induced Reations (open access)

Synthesis of Semiconductor Materials by Radiation Induced Reations

"Progress is reported on: design of a continuous flow system for the irradiation of silane using a Cos5 source; pile irradiation of silane samples at elevated temperatures; investigation of materials other than silane, including nonsilicon compounds as well as those containing the silyl group; modification of the existing vacuum system for handling larger quantities of silane as well as increasing the accuracy of the pressure measurements; and use of an electric discharge for the decomposition of silane. The work performed during the period of this report consisted of the following: 1. Preparation of samples of trichlorosilane and hydrogen and subsequent thermal and irradiation studies, and analysis of these samples. 2. Preparation of mixed samples of silane and argon and subsequent thermal and irradiation studies and and analysis. 3. Outlining of future investigations to be conducted on this project."
Date: October 31, 1961
Creator: Held, Kelman & Goldman, Richard
Object Type: Report
System: The UNT Digital Library
Corrosion and Activity Transfer in the SRE Primary Sodium System (open access)

Corrosion and Activity Transfer in the SRE Primary Sodium System

Abstract: An evaluation extending over a two-year period was made of primary system sodium and of stainless steel, zirconium, and beryllium specimens exposed in the hot and cold legs of a bypass loop in the primary system of the Sodium Reactor Experiment (SRE).
Date: October 30, 1961
Creator: Johnson, H. E.
Object Type: Report
System: The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients (open access)

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 3. Analog Simulation of Reactor Plant Transients

Third part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Object Type: Report
System: The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps (open access)

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 4. Steam Driven Coolant Pumps

Fourth part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. i).
Date: October 23, 1961
Creator: Combustion Engineering, inc. Nuclear Division.
Object Type: Report
System: The UNT Digital Library