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Fuel Cycle Program, a Boiling Water Reactor Research and Development Program. Third Quarterly Report, January 1961-March 1961

Description: The continuing analysis of the VBWR core resulted in refinements in the calculations for reactivity in voids, flux leakage and resonance escape probability. The Zircaloy cladding for 25 fuel assemblies was received and passed inspection. Preliminary measurements of VBWR flux oscillations, used to develop instrumentation and data interpretation techniques, showed random normally-distributed oscillations with a predominant frequency of 0.5 to 1.0 cycles/second. A model for analog computer simulat… more
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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High-Temperatuer Creep Evaluation in Carbon Dioxide Atmosphere : Summary Report, October 1, 1959 to March 31, 1961

Description: This report follows an investigation made to determine creep-rupture data for three sheet materials. Fourteen of sixteen tests were made in an atmosphere of carbon dioxide within hermetically sealed capsules, analyzing the reaction of the three sheet metals: 347 stainless steel, iron-aluminum-chromium alloy designated 261C, and a zirconium-base alloy, AE1H. Minimum creep rate, per cent elongation, and rupture life were determined and reported.
Date: March 31, 1961
Creator: Domagala, R. F.
Partner: UNT Libraries Government Documents Department
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Radioactive contamination in liquid wastes discharged to ground at separations facilities through December 1961

Description: This document summarizes the amounts of radioactive contamination discharged to ground from separations facilities through December 1961. Detailed data for individual disposal sites are presented on a month-to-month basis for the period of July through December 1961. Previous publications of this series are listed in the bibliography and may be referred to for specific information on measurements and radioactivity totals prior to December 1961.
Date: December 31, 1961
Creator: Backman, G. E.
Partner: UNT Libraries Government Documents Department
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The Gamma to Gamma Prime Transformation in the Uranium-Molybdenum System

Description: 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.
Partner: UNT Libraries Government Documents Department
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Health Physics Division Annual Progress Report, July 31, 1961

Description: 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.
Partner: UNT Libraries Government Documents Department
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Sensitivity testing of liquid high explosives

Description: This article describes a test procedure for a liquid high explosive. The liquid to be tested is NTN, a mixture of nitromethane, tetranitomethane, and 1-nitropropane in 52, 33.3, and 14.7 weight per cent. The test is to study the sensitivity of the explosive to shock by firing it in projectiles from a M1A1 155mm howlitzer, with a charge such that it will not exceed 16,500 g`s acceleration.
Date: January 31, 1961
Creator: O`Connell, L.
Partner: UNT Libraries Government Documents Department
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Extrusion of I and E `O` size tubing to evaluate reduction in extruded O.D. and the use of pressed salt follower blocks: Experiment Number U-21

Description: The object of this experiment was to extrude normal uranium hollow billets to I and E `O` size tubing with reduced extruded O.D. and also to evaluate the use of pressed salt follower blocks. Pressed salt (NaCl) follower blocks under various conditions of pre-heat temperature were compared with the standard graphite at 800 F. Even though some yield reduction results, it was concluded that pressed salt follower blocks at 300 F represent a substantial cost reduction due to the extreme price differ… more
Date: January 31, 1961
Creator: Puterbaugh, J.F.
Partner: UNT Libraries Government Documents Department
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Defect-tests of power generating co-extruded fuel rods

Description: The effect of the many parameters which may influence the failure behavior of coextruded fuel material are being evaluated by Reactor & Fuels Research & Development Operation. This knowledge will be helpful in the design, fabrication, and operation of fuel elements so that the hazards and time involved at failure may be minimized. Many of the various tests performed on unirradiated coextruded fuel material have been in isothermal systems. The tests reported here were performed on power generati… more
Date: May 31, 1961
Creator: Goffard, J. W. & Hayden, K. D.
Partner: UNT Libraries Government Documents Department
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Investigations of Radioactive Fuel-Bearing Glasses

Description: "A series of glass compositions containing uranium oxide was investigated to determine fiberizability and physical properties of resultant fibers. The basic properties to be determined were the maximum U/sub 3/O/sub 8/ content in a fiberizable glass and the maximum service temperature of the fibers. Glasses containing 60 wt% U/sub 3/O/sib 8/ were fiberizable; the fibers had strengths of 100,000 psi at 1600 deg F. Fiber-forming equipment was installed at Moun Laboratory to produce glass fibers c… more
Date: July 31, 1961
Creator: Lockwood, P. A.
Partner: UNT Libraries Government Documents Department
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Final Contract Report for September 1, 1959 to August 31, 1960 .

Description: "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.… more
Date: October 31, 1961
Creator: Hyne, James B.; Abrell, J. W.; Gurst, J. E. & Jacobson, Ada L.
Partner: UNT Libraries Government Documents Department
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Development of Clad Ceramic Fuel Plates by Spray-Coating Techniques. Quarterly Technical Progress Report, January-March 1961

Description: The development of plasma-jet spray-coating techniques for producing clad ceramic fuel plates is discussed. Conditions for spraying fused UO/sub 2/ powder were established by depositing cones on stationary substrates. It was found that the arc-gas flow range within which deposition occurs is very narrow. Coatings were made from --200 +325, --270 + 325, and de-slimed -325 mesh fused UO/ sub 2/ powders. To provide data regarding the economics of the process, deposition rates and efficiencies were… more
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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SPACE POWER SYSTEMS TECHNOLOGY STUDIES. RUBIDIUM EVALUATION PROGRAM. Report No. 12. Quarterly Technical Progress Report for Period November 1, 1960 through January 31, 1961

Description: A stainless steel loop test with liquid rubidium was run for 172 hr, and the design temperature of 1510 deg F at approximately 15% vapor quality rubidium in the boiling phase was achieved. The problems of loop operation are discussed, e.g., trapped gas bubbles and argon leakage from the argon-to-water heat exchanger. The rubidium was made to boil, and its boiling point was determined to be 1325 deg F at 33 psia and 1450 deg F at 60 psia. The discrepancy between measured and literature boiling p… more
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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LIQUID-METAL FUEL CONSTITUTION. I. THE SOLUBILITY OF URANIUM IN BISMUTH

Description: High-vacuum, high-temperature equipment for rapid, accurate determinations of liquid-metal solution compositions is described. The solubility of uranium in bismuth was redetermined over the temperature range 300 to 725 deg C with improved precision and temperature calibration. Anomalous solubility effects in uranium-bismuthgraphite systems which could affect the operation of reactors containing graphite are described. (auth)
Date: October 31, 1961
Creator: Schweitzer, D. G. & Weeks, J. R.
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report, January-March 1961

Description: In this investigation, the effect of an ultrasonic field on the maximum nucleate heat flux (burnout) that can be sustained by boiling water in a flow system will be determined. The water will flow in the direction of sound propagation within an annular flow channel bounded on the outside by a glass tube and on the inside by a 0.25-in. OD heating element. The design of the test section and flow system is given. (D.L.C.)
Date: October 31, 1961
Creator: Romie, F.E.
Partner: UNT Libraries Government Documents Department
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Fuel Element Development Program for the Pebble Bed Reactor. Quarterly Progress Report for February 1 to April 30, 1960

Description: Emphasis was shifted in the Pebble Bed Reactor (PBR) Fuel Element Development Program from coatings on the sphere surface to coatings on individual fuel particles as the major deterrent to fission-product leakage. In a highlevel irradiation test, cracks developed in the coatings of specimens coated with pyrolytic carbon and siliconized silicon carbide. In another high-level irradiation test, a graphiie sphere fueled with Al/sub 2/O/sub 3/-coated UO/sub 2/ particles is showing excellent fission-… more
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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INVESTIGATION OF THE CORROSION ASPECTS OF SELECTED ALUMINUM ALLOYS. Pathfinder Atomic Power Plant. Final Report

Description: A literature survey and experimental results from investigations of aluminum corrosion under both static and dynamic test conditions are presented. Static corrosion tests were made on 8001, 8001 + 2.5% Mg and X2219 clad with M400 aluminum alloys. Dynamic corrosion tests were made only on the 8001 alloy. These tests were performed in three identical dynamic corrosion test loops. Initial tests in each loop were made to investigate corrosion behavior in high purity water at high temperatures and h… more
Date: January 31, 1961
Creator: Riskevics, K.
Partner: UNT Libraries Government Documents Department
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REACTOR PLANT SELF-ACTUATED RELIEF VALVE OPERATION. CORE 1, SEED 1. Test Results T-643700

Description: The relief valves that were tested included four each in the reactor coolant loop and in the purification system. Test results are tabulated which indicated that all valves operated at or witai the prescribed limits of 2530 plus or minus 50 psig in the "as left" condition. Most of the valves had to be popped and adjusted several times befors the valves would pop at a pressure within the prescribed limitations. Some of the difficulties encountered during the testing are discussed. (B.O… more
Date: October 31, 1961
Partner: UNT Libraries Government Documents Department
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SNAP II POWER CONVERSION SYSTEM TOPICAL REPORT NO. 8, MERCURY CONDESING RESEARCH STUDIES

Description: Experimental results are summarized for investigations on the condenser fluid mechanics of mercury under zerogravity, two-phase conditions. Conditions required for interfacial stability in tubes were determined as a function of tube diameters. Correlated two-phase pressure drop data are presented as functions of tube inlet Reynolds number and vapor specific volume. Flow regime stability was studied under zero-gravity and 2.55-gravity conditions and at various Reynolds numbers. the effect of non… more
Date: May 31, 1961
Creator: Kiraly, R. J. & Koestel, A.
Partner: UNT Libraries Government Documents Department
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The Study of the Potential Applications of Radioisotope Technology to Water Resource Investigations and Utilization

Description: The study which has been carried out under Contract AT(30-1)2477 has as its objective the review of all work which has been done on the application of radionuclear techniques to research in water resources and supply, the evaluation of this work, and the suggestions of specific experiments which must be performed if these applications are to be extended.
Date: January 31, 1961
Creator: Feely, Herbert W., 1928-
Partner: UNT Libraries Government Documents Department
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Development of Clad Ceramic Fuel Plates by Spray-Coating Techniques. Final Report, Phase I

Description: Activities in a program to develop techniques of plasma spraying clad plate-type UO/sub 2/ fuel elements are reported. The investigation was also directed toward determining the limitations of the process as applied to fuel element fabrication. UO/sub 2/ powder coatings having densities of 90% theoretical were produced. At conditions required for spraying plates, densities of 86% appear to be practical. The rate and efficiency of UO/sub 2/ coating deposition were also determined for various spr… more
Date: October 31, 1961
Creator: Weare, N. E.
Partner: UNT Libraries Government Documents Department
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Elastic Scattering of 31-Mev He3 Ions From Several Elements

Description: The absolute differential cross sections for elastic scattering of 31-Mev He3 ions on Be, Al, Cu, Sn(nat), Sn120, and Bi have been measured in the angular range of approximately 10 to 120 deg in the center-of-mass system. Thin self-supporting foil targets were chosen to span the parameter A 1/3, where A is the target mass number. The first excited states of the isotopes of the above elements had sufficient energy separation from the ground state to enable elastic scattering to be resolved from … more
Date: December 31, 1961
Creator: Igo, George; Markowitz, Samuel S. & Vidal, Jose G.
Partner: UNT Libraries Government Documents Department
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