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

Description: 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.
Partner: UNT Libraries Government Documents Department
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The Beta-Gamma Surface Dosage Rate from Natural Uranium

Description: 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
Partner: UNT Libraries Government Documents Department
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Boiling Homogeneous Reactor for Power and U233 Production: Reactor Design and Feasibility Problem

Description: 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.
Partner: UNT Libraries Government Documents Department
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Cost Estimate for the Food Irradiation Reactor

Description: 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.
Partner: UNT Libraries Government Documents Department
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Design and Economic Evaluation of Fixed Blankets for Fast Reactors

Description: 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.
Partner: UNT Libraries Government Documents Department
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Life Tests of Tungsten and Tantalum Filaments in Ion Gauges

Description: 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.
Partner: UNT Libraries Government Documents Department
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Radiation Damage in Boron Carbide

Description: 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
Partner: UNT Libraries Government Documents Department
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N-Reactor Operational Safety Review

Description: 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.
Partner: UNT Libraries Government Documents Department
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SM-1 Research and Development Program, Activity Buildup Program Task 1 : final report February 1958 to June 1959

Description: 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.
Partner: UNT Libraries Government Documents Department
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SM-2 Fuel Element Welding Development : Task 5.0

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Stress Corrosion Cracking in Uranium-Molybdenum Alloys

Description: 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.
Partner: UNT Libraries Government Documents Department
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