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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

Partner: UNT Libraries Government Documents Department

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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.

Partner: UNT Libraries Government Documents Department

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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.

Partner: UNT Libraries Government Documents Department

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Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2

Gamma-Ray Spectrum diagrams.

Date: August 1964

Creator: Heath, R. L.

Partner: UNT Libraries Government Documents Department

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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.

Partner: UNT Libraries Government Documents Department

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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 compare… more

Date: August 9, 1949

Creator: Bush, W. E.

Partner: UNT Libraries Government Documents Department

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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.

Partner: UNT Libraries Government Documents Department

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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

Partner: UNT Libraries Government Documents Department

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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

Partner: UNT Libraries Government Documents Department

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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.

Partner: UNT Libraries Government Documents Department

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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.

Partner: UNT Libraries Government Documents Department

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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

Partner: UNT Libraries Government Documents Department

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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.

Partner: UNT Libraries Government Documents Department

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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.

Partner: UNT Libraries Government Documents Department

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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.

Partner: UNT Libraries Government Documents Department

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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.

Partner: UNT Libraries Government Documents Department

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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

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

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

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

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

Design and Economic Evaluation of Fixed Blankets for Fast Reactors

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

Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2

Cost Estimate for the Food Irradiation Reactor

Life Tests of Tungsten and Tantalum Filaments in Ion Gauges

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

The Beta-Gamma Surface Dosage Rate from Natural Uranium

Radiation Damage in Boron Carbide

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

Stress Corrosion Cracking in Uranium-Molybdenum Alloys

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

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

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

Research and Developement on Fabrication of Pin and Lid Detectors and the Dry Run Interface System, Final Report

N-Reactor Operational Safety Review

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

SM-1 Research and Development Program, Activity Buildup Program Task 1 : final report February 1958 to June 1959

SM-2 Fuel Element Welding Development : Task 5.0