Degree Department

Degree Level

Comparison of Optimum Natural Uranium Nuclear Power Plant and Optimum Enriched Uranium Nuclear Power Plant (open access)

Comparison of Optimum Natural Uranium Nuclear Power Plant and Optimum Enriched Uranium Nuclear Power Plant

Report that "compares the designs of an optimum natural uranium power plant and an optimum partially enriched uranium power plant, both using CO2 as a coolant" (p. 1). Includes a description of each plant's design, construction, and economic considerations.
Date: August 1958
Creator: Kaiser Engineers
Object Type: Report
System: The UNT Digital Library
A Summary of Strontium 90 Analyses for Monthly Pot and Precipitation Collections (open access)

A Summary of Strontium 90 Analyses for Monthly Pot and Precipitation Collections

Report summarizing strontium 90 analyses collected throughout the world in order to determine the relationship between precipitation and nuclear fallout.
Date: August 18, 1958
Creator: U.S. Atomic Energy Commission. Health and Safety Laboratory.
Object Type: Report
System: The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1971 (open access)

Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1971

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: August 1971
Creator: Oak Ridge National Laboratory
Object Type: Report
System: The UNT Digital Library
Design and Economic Evaluation of Fixed Blankets for Fast Reactors (open access)

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.
Object Type: Report
System: The UNT Digital Library
Self-Sustained Hydrodynamic Oscillations in a Natural Circulation Two-Phase-Flow Boiling Loop (open access)

Self-Sustained Hydrodynamic Oscillations in a Natural Circulation Two-Phase-Flow Boiling Loop

Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
Date: August 1965
Creator: Jain, Kamal C.
Object Type: Report
System: The UNT Digital Library
In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C (open access)

In-Pile Loop Corrosion Experiments with Uranyl Sulfate Solutions at 235 and 250 C

Report presenting in-pile loop experiments DD, EE, FF, GG, L-412, L-413, and L-418, which were seven of a series designed to test the radiation corrosion of zirconium, titanium, and stainless steel alloys in solutions under various conditions of radiation intensity, temperature, solution composition, and velocity of flow. Steel specimens exposed in the loop cores showed increases in corrosive attack over that expected out-of-radiation.
Date: August 15, 1963
Creator: Jenks, G. H. & Baker, J. E.
Object Type: Report
System: The UNT Digital Library
Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2 (open access)

Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2

Gamma-Ray Spectrum diagrams.
Date: August 1964
Creator: Heath, R. L.
Object Type: Report
System: The UNT Digital Library
Cost Estimate for the Food Irradiation Reactor (open access)

Cost Estimate for the Food Irradiation Reactor

Study conducted for the U. S. Army Reactors Branch of reactors for the irradiation of food.
Date: August 23, 1956
Creator: Jaffe, R. J.; Larson, A. M., Jr.; Leyse, C. F.; Mason, E. E. & Sliger, R. W.
Object Type: Report
System: The UNT Digital Library
Life Tests of Tungsten and Tantalum Filaments in Ion Gauges (open access)

Life Tests of Tungsten and Tantalum Filaments in Ion Gauges

Results of an investigation carried on for the following purposes: (1) To determine the relative life of filaments when operated at low emission (low temperatures) as compared to those operated at high emission values. (2) To determine the nature of the dependence of life upon the initial diameter of the filament. (3) To determine the effect of varying concentrations of water vapor and air upon the life of the filaments. (4) To determine the relative life characteristics of tantalum as compared to tungsten.
Date: August 9, 1949
Creator: Bush, W. E.
Object Type: Report
System: The UNT Digital Library
Boiling Homogeneous Reactor for Power and U233 Production: Reactor Design and Feasibility Problem (open access)

Boiling Homogeneous Reactor for Power and U233 Production: Reactor Design and Feasibility Problem

Summary report of the study, research, problems and solutions developed in the final ten-weeks period of the school term for a group of men representing various scientific and engineering fields.
Date: August 1954
Creator: Zeitlin, H. R.; Bertini, H. W.; Bourgeois, W. F.; Calvin, J. N.; Engel, J. R.; Farbman, G. H. et al.
Object Type: Report
System: The UNT Digital Library
The Beta-Gamma Surface Dosage Rate from Natural Uranium (open access)

The Beta-Gamma Surface Dosage Rate from Natural Uranium

From summary: "Report discussing the beta-gamma dosage rate at the surface of a natural uranium disc. Measurements were taken using a Ryerson electrometer and an extrapolation ionization chamber."
Date: August 22, 1949
Creator: Kalmon, Ben
Object Type: Report
System: The UNT Digital Library
Radiation Damage in Boron Carbide (open access)

Radiation Damage in Boron Carbide

From introduction: "Report describing the study of radiation damage in boron carbide with an integrated thermal neutron flux of 3x10^20 neutrons/cm² in the Materials Testing Reactor (MTR)."
Date: August 18, 1953
Creator: Tucker, Charles W., Jr. & Senio, Peter
Object Type: Report
System: The UNT Digital Library
Initial Operation and Testing of the Army Package Power Reactor APPR-1 (open access)

Initial Operation and Testing of the Army Package Power Reactor APPR-1

Startup and initial operation of the APPR-1 and summary of the results of the test program on the reactor.
Date: August 9, 1957
Creator: Meem, J. L.
Object Type: Report
System: The UNT Digital Library
Stress Corrosion Cracking in Uranium-Molybdenum Alloys (open access)

Stress Corrosion Cracking in Uranium-Molybdenum Alloys

Investigation conducted to determine the cause of cracking, during tension, on the surface of tensile specimens of uranium-molybdenum alloys.
Date: August 12, 1963
Creator: Pridgeon, J. W.
Object Type: Report
System: The UNT Digital Library
Determining the "State of Charge" of Nickel-Cadmium Batteries by Farad Capacitance Measurements (open access)

Determining the "State of Charge" of Nickel-Cadmium Batteries by Farad Capacitance Measurements

From abstract: "A rapid simple method has been developed for determining state of charge of the widely used nickel-cadium rechargeable battery. The method described is based on the experimentally verified relationship between farad capacitance and state of charge."
Date: August 1968
Creator: Latner, Norman
Object Type: Report
System: The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962 (open access)

Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962

From introduction: "This is the eleventh 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: August 1962
Creator: Pennington, R. T.
Object Type: Report
System: The UNT Digital Library
U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1 (open access)

U.S. Reactor Containment Technology: a Compilation of Current Practice in Analysis, Design, Construction, Test, and Operation, Volume 1

First volume of a compilation of information about reactor containment, written by experts from a variety of organizations.
Date: August 1965
Creator: Cottrell, William B. & Savolainen, A. W.
Object Type: Report
System: The UNT Digital Library
Analytical Studies of Transient Effect in Fast Reactor Fuels: [Part] 1 (open access)

Analytical Studies of Transient Effect in Fast Reactor Fuels: [Part] 1

From abstract: "An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined and possible mechanisms of failure are analyzed."
Date: August 1962
Creator: Osborn, R. B. & Sherer, D. B.
Object Type: Report
System: The UNT Digital Library
Research and Developement on Fabrication of Pin and Lid Detectors and the Dry Run Interface System, Final Report (open access)

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.
Object Type: Report
System: The UNT Digital Library
N-Reactor Operational Safety Review (open access)

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.
Object Type: Report
System: The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961 (open access)

Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: First Quarterly Report, October-December 1961

Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date: August 15, 1963
Creator: Leitz, F. J.
Object Type: Report
System: The UNT Digital Library
Phase 3 Design Analysis for the Army Package Power Reactor: Volume 1 (Design Analysis) (open access)

Phase 3 Design Analysis for the Army Package Power Reactor: Volume 1 (Design Analysis)

From foreword: "This report consists of two volumes which comprise the Phase III Design Analysis for the Army Package Power Reactor." The first volume discusses design analysis of the reactor.
Date: August 15, 1956
Creator: unknown
Object Type: Report
System: The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: February-April 1960 (open access)

Homogeneous Reactor Project Quarterly Progress Report: February-April 1960

Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. It includes descriptions of progress and studies conducted during the report period, with tables, illustrations, and photographs.
Date: August 9, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Object Type: Report
System: The UNT Digital Library
Uranium Hydrogeochemical and Stream Sediment Reconnaissance of the Dubois NTMS quadrangle, Idaho/Montana, Including Concentrations of Forty-Five Additional Elements (open access)

Uranium Hydrogeochemical and Stream Sediment Reconnaissance of the Dubois NTMS quadrangle, Idaho/Montana, Including Concentrations of Forty-Five Additional Elements

This report presents uranium and other elemental data resulting from the Hydrogeochemical and Stream Sediment Reconnaissance (HSSR) of the Dubois NTMS quadrangle in Idaho and Montana. Totals of 1024 water samples and 1600 sediment samples were collected from 1669 locations in the Dubois quadrangle. Water samples were taken at streams, springs, and wells; sediment samples were collected from streams and springs.
Date: August 1980
Creator: LaDelfe, Carol M.
Object Type: Report
System: The UNT Digital Library