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Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1961 - December 1, 1961

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: December 30, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Partner: UNT Libraries Government Documents Department
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Shipboard Cobalt-60 Radiopasteurizer for Marine Products

Description: Report issued by the Brookhaven National Laboratory discussing the shipboard cobalt-60 irradiator. As stated in the introduction, "this report discusses the conceptual design of a cobalt-60 shipboard irradiator for use to improve the keeping quality of fish landed aboard commercial fishing trawlers operating out of ports along the eastern seaboard of the commercial United States" (p. 1). This report includes tables, and illustrations.
Date: June 30, 1963
Creator: Manowitz, B.; Kuhl, A. O.; Galanter, L.; Armel, J.; Black, K. M.; Klaassen, W. J. et al.
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report: May 1966

Description: Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during May 1966. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: June 30, 1966
Creator: Adams, R. M. & Glassner, A.
Partner: UNT Libraries Government Documents Department
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Cobalt-60 Bulk Grain Irradiator: Study Report

Description: Report issued by the Brookhaven National Laboratory discussing bulk grain irradiators. As stated in the abstract, "this report presents the results of a study to conceive, evaluate, review and estimate costs for a number of suitable designs for a Cobalt-60 Bulk Grain Irradiator; select a preferred type; and establish required criteria for future detail design and construction of the selected concept" (p. ii). This report includes tables, and illustrations.
Date: June 30, 1963
Creator: Brookhaven National Laboratory
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor, Technical Feasibility Report

Description: Report concerning the technical feasibility of a full-scale Liquid Metal Fuel Reactor, including metallurgical, mechanical, and engineering evaluations.
Date: June 30, 1955
Creator: Babcock & Wilcox Company
Partner: UNT Libraries Government Documents Department
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The Strain Aging and Heat Treatment Properties of N-Reactor Connector Tubes

Description: Report regarding the determination of "the susceptibility to strain aging and the effect of stress-relief annealing on the properties of N-reactor connecting tubes made from ASTM A-106 Grade B high carbon steel" (p. 2).
Date: July 30, 1963
Creator: Pessl, H. J.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Annual Progress Report, July 1, 1960

Description: Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Date: September 30, 1960
Creator: Oak Ridge National Laboratory. Metallurgy Division.
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

Description: From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date: September 30, 1959
Creator: Linenberger, G. A.
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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Berkeley Proton Linear Accelerator

Description: Construction of a linear accelerator which increases the energy of protons from a 4 Mev Van de Graaff injector to a final energy of 31.5 Mev.
Date: November 30, 1948
Creator: Alvarez, Luis W.; Bradner, Hugh; Gordon, Hayden; Panofsky, Wolfgang K. H.; Richman, Chaim & Woodyard, John R.
Partner: UNT Libraries Government Documents Department
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A Neutron Absorption Alignment Chart

Description: From introduction: "Neutron absorption alignment chart for the measurement of neutron flux density."
Date: July 30, 1957
Creator: Nisle, Robert G.
Partner: UNT Libraries Government Documents Department
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EDP Procedures in Technical Library Operations

Description: Systems for circulation control, book ordering, journal renewal, printing a book catalog, preparing monthly acquisitions lists.
Date: July 30, 1963
Creator: Griffin, Hillis L.
Partner: UNT Libraries Government Documents Department
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Program Study Report Plutonium Fuel Cycle

Description: From introduction: "The development and demonstration of the natural uranium reprocessed plutonium cycle in power reactors is an important phase of the peaceful applications of nuclear energy."
Date: July 30, 1956
Creator: Albaugh, F. W. & Fryar, R. M.
Partner: UNT Libraries Government Documents Department
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Thermal Analysis of Type 3 Elements in the SM-1, SM-1A and PM-2A Cores

Description: Report describing a study which analyzed thermal characteristics of Type 3 elements planned for installation in the SM-1, SM-1A and PM-2A plants, for both steady state and loss of flow transient conditions. Results of this analysis for steady state conditions indicate that the SM-1, SM-1A and PM-2A Type 3 cores will operate safely at design and scram conditions.
Date: March 30, 1962
Creator: Davidson, S. L. & Segalman, I.
Partner: UNT Libraries Government Documents Department
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Preliminary Design Report - Title 1 on Mobile Gamma Irradiator

Description: Introduction: The Mobile Gamma Irradiator is a semi-production demonstration unit capable of being transported from one area to another for use in irradiating fruit and farm produce, with the capability of furnishing dosages in the pasteurization range.
Date: October 30, 1964
Creator: Lowenberg, H. & Allentuck, J.
Partner: UNT Libraries Government Documents Department
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P-V-T Relationships of BF₃ Gas

Description: Abstract: A generalized equation of state developed by Gouq-Jen Su and Chien-Hou Chang is used for predicting P-V-T behavior of BF3 at high gas densities.
Date: July 30, 1960
Creator: Smith, C. R. F.
Partner: UNT Libraries Government Documents Department
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Valve Stem Freeze Seal for High-Temperature Sodium

Description: Abstract: An experimental study of valve stem freeze seals was undertaken as part of the effort to develop components for high temperature service in advanced sodium-cooled reactor systems.
Date: July 30, 1960
Creator: McDonald, J. S.
Partner: UNT Libraries Government Documents Department
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OMR (Piqua) Unitized Control-Safety Rod Prototype Tests

Description: Abstract: A unitized magnetic jack driven control-safety rod has been developed for the 45.5 thermal megawatt organic moderated reactor (Piqua).
Date: June 30, 1960
Creator: Howell, J. D. & Weeks, C. C.
Partner: UNT Libraries Government Documents Department
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High Temperature Corrosion of Some Metals and Ceramics in Fluorinating Atmospheres

Description: Abstract: The results of this investigation leave little doubt that diffusion of the fluorinating gas along the grain boundaries of the nickel fluoride film to react at the metal-scale interface is the primary mechanism of attack upon pure nickel and its more promising alloys.
Date: September 30, 1960
Creator: Hale, C. F.; Barber, E. J.; Bernhardt, H. A. & Rapp, Karl E.
Partner: UNT Libraries Government Documents Department
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SRE Fuel Element Damage: An Interim Report

Description: Abstract: During the course of power run 14 on the Sodium Reactor Experiment (SRE) at low power, the temperature difference among various fuel channels was found to be undesirably high. Normal operating practices did not succeed in reducing this temperature difference to acceptable values and on July 26, 1959, the run was terminated.
Date: November 30, 1959
Creator: Jarrett, A. A.
Partner: UNT Libraries Government Documents Department
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Corrosion and Activity Transfer in the SRE Primary Sodium System

Description: Abstract: An evaluation extending over a two-year period was made of primary system sodium and of stainless steel, zirconium, and beryllium specimens exposed in the hot and cold legs of a bypass loop in the primary system of the Sodium Reactor Experiment (SRE).
Date: October 30, 1961
Creator: Johnson, H. E.
Partner: UNT Libraries Government Documents Department
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