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Electrostatic Classification of Submicron Airborne Particles : Final Report, August 16, 1961 to January 31, 1963

Description: From abstract: "This project was a study of electrostatic classification of submicron aerosols. Classification of particles as small as 0.006-[mu]-diameter was shown to be feasible, and good classification of atmospheric dust was achieved. However, a practical solution to the problem of overlapping between particles larger and smaller than 0.1 [mu], the point of minimum electric mobility, was not found."
Date: January 31, 1963
Creator: Langer, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Magnetic Properties of Insulators : Quarterly Report No. 8 Covering the Period from November 16, 1962 to February 15, 1963

Description: The following quarterly progress report covers the period from November 16, 1962 to February 15, 1963. This report summarizes three activities that study the ratio of the maximum absorption of the K band to the maximum absorption of the F band has been made in additively colored and [gamma]-irradiated rubidium chloride.
Date: March 1, 1963
Creator: Markham, Jordan J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Magnetic Properties of Insulators : Quarterly Report No. 9 Covering the Period from February 16, 1963 to May 15, 1963

Description: The following quarterly report covers the period during February 16 to May 15, 1963. This report is divided into sections covering the separate activities during this period, studying the thermal behavior of the F-center in RbCl.
Date: June 5, 1963
Creator: Markham, Jordan J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scintillation spectrometer measurements of capture gamma rays from natural elements : sixth quarterly report covering the period November 1, 1962 to January 31, 1963

Description: This report discusses many low energy neutron capture gamma ray spectra from many elements. Also, a series of neutron capture gamma ray spectra from a wide variety of meteorite and terrestrial rock samples were obtained.
Date: 1963
Creator: Greenwood, Reginald C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Scintillation spectrometer measurements of capture gamma rays from natural elements : seventh quarterly report covering the period February 1, 1963 to April 30, 1963

Description: A report focused on obtaining further neutron capture gamma ray spectra for inclusion in the Atlas, and in conducting subsidiary experiments to determine the cause of the anomalous broad peak structure which was reported in ARF 1193-20.
Date: 1963
Creator: Greenwood, Reginald C.; Reed, J. H. & Kolar, R. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fast Neutron Interactions with Li⁶ and Li⁷

Description: Abstract: "Measurements have been made of the cross sections for the reactions Id-6(n, dn)He-4 and Li-7(n, tn)He-4 over an incident neutron energy range of 5 - 14 MeV. The energy and angular distributions of all reaction products were determined."
Date: July 18, 1963
Creator: Rosen, Louis
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Core Instrumentation Development Program Quarterly Progress Report June - September 1963

Description: Introduction: The objective of Project Agreement 22 is to determine the feasibility of covering the complete reactor neutron flux start range from 10(3) - 5 x 10(13) nv by using in-core chambers. The counting mode of operating will be used at low neutron fluxes and the root mean square voltage fluctuation mode will be used at high neutron flux levels. Experiments have been run utilizing various ion chambers, gases, gas pressures, voltage, and cables to measure sensitivities and range operating … more
Date: October 1963
Creator: DuBridge, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: July 1 - September 30, 1963

Description: A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. Quarterly progress: The densitometry procedure (for measurement of alpha autoradiographs of fuel pellets) has been modified to eliminate the need for a second emulsion. The existence of a problem of latent image fading and non-reciprocity of … more
Date: October 15, 1963
Creator: Robkin, M. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Transition Boiling Heat Transfer Program; First Quarterly Progress Report, February - March 1963

Description: Introduction: The Transition Boiling Heat Transfer Program is sponsored jointly by the USAEC and Euroatom and is being conducted by the General Electric Company. The work commenced on this program February 11, 1963. The objective of this program is to perform basic investigation and measurement of the transition boiling regime in high pressure bulk boiling water flows, with particular emphasis i the high range of steam qualities.
Date: April 15, 1963
Creator: Tippets, F. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Accurate Nuclear Fuel Burnup Analyses; Eighth Quarterly Progress Report, (September - November 1963)

Description: The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: December 1, 1963
Creator: Rider, B. F.; Ruiz, C. P.; Luke, P. S., Jr.; Peterson, J. P., Jr. & Smith, F. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Two-Phase Pressure Losses Quarterly Progress Report: Seventh Quarter, August 12, 1963 - November 11, 1963

Description: Technical report describing that the pressure drop along an annular channel with dimensions D(1) = 0.375 inch; D(2) = 0.875 inch, L = 70 inches. Flow was vertical and upward, and only the internal surface was heated. Subcooled conditions existed at the inlet, with two-phase conditions at the exit. Groups of three radial spacer pins on 18-inch centers along the channel, held the inner surface concentric with the outer surface. The single phase loss coefficient for each spacer group is K(8) = 0.2… more
Date: December 2, 1963
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Statistical Techniques Used in the Specific Zirconium Alloy Design Program

Description: Technical report describing the statistically designed empirical approach being used to choose a candidate Zr alloy optimum with respect to corrosion and hydriding rates in steam and having acceptable mechanical properties. The statistical techniques used and the reasons for their use are discussed in detail, with emphasis on the estimation of corrosion rates. Estimation of response surfaces is also considered.
Date: November 11, 1963
Creator: Jaech, John L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Tube-To-Tubesheet Welding Development Programs to 30 Megawatt Prototype Sodium Intermediate heat Exchanger and Steam Generator

Description: Special welding techniques for joining Inconel weld overlays on type 316 stainless steel tubesheets and channels are described. The program for the development of the required welding procedures are divided into three specific programs: overlaying Inconel filler Metal 82 on type 316 stainless steel, welding type 316 stainless steel tubes to a type 316 stainless steel tubesheet, and welding Inconel-type 316 stainless steel composite tubes to Inconel weld overlaid type 316 tubesheets. Shock tests… more
Date: 1963
Creator: Alco Products (Firm).
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Residual and Fission Gas Release from Uranium Dioxide

Description: Abstract: Residual and fission gas release from UO2 were studied in the laboratory and in in-reactor experiments. Arc-fused powder and sintered pellets were used to determine the rate of evolution and types of residual gases as a function of temperature. Fission gas release was related to the average UO2 temperature and fission gas release calculations were made using the latest thermal conductivity values, isotopic half lives, and branching ratios available in the literature. The results obtai… more
Date: July 15, 1963
Creator: Spalaris, C. N. & Megerth, F. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Grain Growth of UO2. Part I

Description: Abstract: (1) Grain growth in UO2 pellets was studies between 100 C and 2600 C. The pellets were encapsulated in small vacuum-tight tungsten containers in an argon atmosphere. (2) The grain size-time relationship could be expressed by an equation. A low exponent, m>_ 1/3, was found in those experiments and is related to the type of UO2 investigated. An activation energy of 65 kcal/mole was obtained for the grain growth process. The time exponent, m, increased with increasing temperature if the … more
Date: August 15, 1963
Creator: Hausner, H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Physics Design of the Mixed Spectrum Critical Assembly

Description: Summary: The Mixed Spectrum Superheater (MSSR) is an integral superheater reactor in which boiling occurs in an annular Boiling Water Reactor section and steam in superheated in an unmoderated fast section in the center. A Mixed Spectrum Critical Assembly (MSCA) to be operated at the Vallecitos Atomic Laboratory has been designed to mock up a 75-150 MWe prototype MSSR. The principal experimental measurements aimed at proving the feasibility of the MSSR concept include power distribution, Dopple… more
Date: August 1963
Creator: Reynolds, A. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Measurement of Fission Gas Pressure in Operating Fuel Elements: Post-Irradiation Examination

Description: Summary: Two UO2-filled stainless steel clad fuel rods in which fission gas pressure was measured during irradiation have been subjected to post irradiation examination. Results of free gas analysis and metallographic examination are in general agreement with observed pressures reported previously. Calculated fuel surface temperatures based on extent of fuel recrystallization indicate that in a one-half inch diameter fuel rod with 0.014 inch diametral clearance operated at a maximum heat flux o… more
Date: September 20, 1963
Creator: Reynolds, M. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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High Power Density Development Project: Potter Meter Calibration and Instrumented Fuel Bundle Pressure Drop

Description: Summary: Technical report describing the testing of eight Potter Meters, for metering inlet flow and measuring exit steam qualities in the Consumers Big Rock Point Instrumented Fuel Assemblies, were individually calibrated for flow and pressure drop up to 500 gpm in the low temperature (130 F) fluid flow facility. The flow calibration comparison made with an ASME orifice installation, agreed to within + - 1 percent among seven of the meters, and meter Serial No. 8 was 2.8 percent lower than th… more
Date: July 26, 1963
Creator: Polomik, E. E. & Swan, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Sixteenth Quarter, May-July 1963

Description: From introduction: "This is the sixteenth in a series of quarterly reports which cover the progress and results from the conceptual designs, economic evaluations and research and development work performed by the General Electric Company as part of Contract AT(01-3)-189, Project Agreement No. 13."
Date: August 15, 1963
Creator: Flock, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Multirod (Four Rod) Critical Heat Flux at 1000 PSIA

Description: Technical report describing the four-rod heat flux experiments that are a part of a continuing program of study of the critical heat flux, or burnout phenomenon in order that water cooled reactors can be designed with a maximum of safety and efficiency. During heat transfer with boiling, there is a particular heat flux, for a given set of flow conditions and geometry, above which the nucleate boiling process begins to break down. This breakdown of the nucleate boiling process is known as burno… more
Date: September 1963
Creator: Hench, John E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Maritime Loop Irradiation Program for Savannah I Fuel Post-Irradiation Examination of SI5BM Fuel Assembly

Description: Abstract: A stainless steel clad 9-rod assembly fabricated by The Babcock & Wilcox Company was irradiated in a boiling water loop of the General Electric Test Reactor. A post-irradiation examination revealed no significant dimensional changes on the fuel rods. the results of mass spectrometric analysis made of the pelletized UO2 fuel indicated a maximum burnup of 11,500 MWD/tonne was attained by Rod B-4 during the exposure.An x-ray diffraction examination of an unirradiated fuel sample revealed… more
Date: November 7, 1963
Creator: Mathay, P. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fuel Failure Examinations and Analyses in the High Power Density Program

Description: Summary: The High Power Density Project includes a comprehensive fuel development program which has the objective of developing and demonstrating the performance of a nuclear reactor core having a high power density, long fuel life, and low fabrication cost. The fuel program is made up of two principal tasks. Task 1A consists of irradiation tests in the VBWR of Type 304 stainless steel clad, UO2 pellet type fuel rods fabricated by current commercial processes. Task 1B consists of the investigat… more
Date: September 16, 1963
Creator: Arlt, W. H. & Vandenberg, S. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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