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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.
System:
The UNT Digital Library
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
System:
The UNT Digital Library
SM-1 Research and Development Program, Activity Buildup Program Task 1 : final report February 1958 to June 1959
Abstract: The results of activity buildup studies in the SM-1 (APPR-1) performed from February 1958 to January 1959 are reported. Data are presented on the extent, nature, and mechanism of the buildup of long-lived gamma emitting nuclides in the reactor primary system. Mathematical equations to describe the activity buildup are derived. Radiation levels after reactor shutdown are presented, as well as the predicted radiation levels at the end of core life.
Date:
August 10, 1959
Creator:
Brown, William S.; Bergen, C. Richard.; Bergmann, Carl A.; Chupak, Julius.; Fitzsimmons, Susanne R. & Grant, Louis G.
System:
The UNT Digital Library
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
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
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2
Gamma-Ray Spectrum diagrams.
Date:
August 1964
Creator:
Heath, R. L.
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
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.
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
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.
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
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
System:
The UNT Digital Library
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
System:
The UNT Digital Library
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
System:
The UNT Digital Library
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.
System:
The UNT Digital Library
SM-2 Fuel Element Welding Development : Task 5.0
Abstract: Development of welding processes for stainless steel fuel elements, previously initiated by Alco Products, was continued in Task 5. Three objectives were accomplished; (1) development of a suitable reference welding process, (2) evaluation by out-of-pile tests of the structural integrity of reference welded fuel elements, and (3) preparation of specifications and fabrication procedures for the reference welding process.
Date:
August 11, 1960
Creator:
Harris, R. L.
System:
The UNT Digital Library