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Summary Report of Physics Measurements on SM-1 Core I

Description: Abstract: This technical report summarizes all core physics experiments performed on SM-1 Core I and SM-2 Rearranged and Spiked Core I throughout core life. These measurements were obtained on site during the 16.4 MWYR lifetime of SM-1 Core I and 1.6 MWYR lifetime of SM-1 Rearranged and Spiked Core I. SM-1 Core I was the first stainless steel - UO2 dispersion core to burn out in the Army Nuclear Power Program. Experimental techniques are described and a complete history of fuel movements in the core presented. Measurements include control rod bank positions during all core conditions, temperature and pressure coefficients, control rod calibrations, transient poison effects, source multiplication, and stuck rod positions. The effect of core rearrangement and spiking on core reactivity and core life is also reported. Applicable measurements from the SM-1 zero power experiments are included.
Date: February 6, 1962
Creator: Weiss, S. H.
Partner: UNT Libraries Government Documents Department
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A 37,500 KW Power Reactor with Competitive Possibilities

Description: The following report follows the study on economics of nuclear power generation using a light water reactor.
Date: February 26, 1954
Creator: Thompson, W. I. & Cohen, Karl
Partner: UNT Libraries Government Documents Department
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Dibutyl Carbitol Solvent Extraction of Polonium-210 from Nitric Acid Solutions of Irradiated Bismuth

Description: Abstract: "A continuous countercurrent solvent extraction process utilizing dibutyl carbitol as the extractant has been developed for separating 210Po from large amounts of associated bismuth. Both laboratory and pilot plant data demonstrate the process is a suitable headend step in recovery of kilogram quantities of 210Po. Typically, the extraction process recovers over 98% of the 210Po, essentially free from bismuth (Bi DF>1500), in a dilute HNO3 solution suitable as a starting material for final concentration and purification steps."
Date: February 1968
Creator: Schulz, Wallace W. & Richardson, G. L.
Partner: UNT Libraries Government Documents Department
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Nitride Fuels for Fast Breeder Reactors: Fuel Cycle Considerations

Description: This report follows a study that was made to develop comparative fuel cycle costs for nitride and carbide fuels in a 1000 MWe sodium-cooled fast-breeder reactor.
Date: February 1968
Creator: Fletcher, John F. & Greenborg, Jess
Partner: UNT Libraries Government Documents Department
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The Elimination of Microwave Reflections

Description: Abstract: "The reflections of microwaves from the walls of a plasma-containing vessel are studied. The probable cause of the reflections is discussed, and several suggestions are made for eliminating the reflections from the waveguide in the vessel and particularly from the pyrex vessel wall and copper tubing surrounding the pyrex. Quarter-wave-thick carbon-filled plastics or glasses having a very low vapor pressure room most promising when placed inside the pyrex cylinder. BaTiO3 appears to be an excellent material when placed outside the vacuum."
Date: February 1, 1955
Creator: Beard, David
Partner: UNT Libraries Government Documents Department
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Transistorized Trip Circuit for Critical Assemblies

Description: Abstract: A transistor trip circuit intended for critical assemblies and which provides maximum safety against human error or component failure is described.
Date: February 24, 1958
Creator: Wade, E. J. & Davidson, D. S.
Partner: UNT Libraries Government Documents Department
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The NAA 47 U - 10 Mo Fuel Irradiation Program for HNPF Core 1

Description: Abstract: Atomics International conducted a fuel irradiation program to investigate and define the behavior of U-10 Mo fuel at the temperatures and fission rates anticipated in Hallam Nuclear Power Facility (HNPF) Core I.
Date: February 1, 1965
Creator: Schmitt, A. R.; Willard, R. M. & Magnus, D. K.
Partner: UNT Libraries Government Documents Department
open access

Performance of Cesium Thermionic Diodes Operated in Series-Parallel Circuits

Description: Introduction: The purpose of this experiment is to determine the loss of electrical power output due to operating many unequally-heated cesium diodes, connected in series and parallel circuits.
Date: February 1, 1963
Creator: Holland, J. W.
Partner: UNT Libraries Government Documents Department
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Flow Stability of Gas-Solids Suspensions: Final Report

Description: From abstract: One of the principal purposes of the work reported was to study the stability of gas-solids suspensions in the presence of a thermal gradient. Previously reported experience with unstable suspensions is summarized.
Date: February 1964
Creator: Wachtell, G. P. & Waggener, J. P.
Partner: UNT Libraries Government Documents Department
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An Industrial Gamma Irradiator for Medical Supplies

Description: From foreword: This report presents the preliminary design of an industrial gamma irradiator for the sterilization of medical supplies.
Date: February 19, 1960
Creator: Frankfort, J. Harry; Haram, S. & Wallach, S.
Partner: UNT Libraries Government Documents Department
open access

Flux Control for Irradiation Experiments

Description: Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control.
Date: February 1, 1965
Creator: McCarty, W. K.
Partner: UNT Libraries Government Documents Department
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Fatigue Characteristics of 37-Tube, Modular, Steam Generator Head

Description: Abstract: This report presents the pertinent results of a series of fatigue tests relating to the evaporator and superheater 37-tube module heads for the sodium heated steam generator described in NAA-SR-9826.
Date: February 20, 1965
Creator: Lemcoe, M. M.
Partner: UNT Libraries Government Documents Department
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Organic Moderated Reactor Experiment : Safeguards Summary

Description: Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.
Date: February 1, 1958
Creator: Sletten, H. L. & Blue, L. R.
Partner: UNT Libraries Government Documents Department
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Fluidization in Tapered Beds

Description: Abstract: The concept of a tapered fluidized bed is explored briefly. Data are given showing that in bench scale apparatus a tapered bed gives better fluidization with some materials that are difficult to fluidize in a conventional cylindrical bed.
Date: February 14, 1958
Creator: Rossmassler, W. R. & Harris, R. L.
Partner: UNT Libraries Government Documents Department
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Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator

Description: Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.
Date: February 28, 1961
Creator: Webster, L. J.
Partner: UNT Libraries Government Documents Department
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Design Modifications to the SRE during FY 1960

Description: Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Partner: UNT Libraries Government Documents Department
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