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Fabrication and Properties of Extruded Silver-Cadmium Control Rods

Description: The production of cross-type control rods having a span of 4-7/8 in., and an arm thickness of 1/8 in., was studied. Extrusion techniques were developed for producing cross-type control rods from each of two alloys; one containing 75% silver-25% cadmium, and the other containing 67% silver-30% cadmium-3% copper. Fabrication of the extruded crosses into clad control rods for the Mark I naval reactor was attempted. A set of unclad control rods for the Zero Power Reactor was produced. The effect of… more
Date: January 1952
Creator: Dwight, Austin E. (Austin Elbert), 1919-
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemistry Division, Section C-II, Summary Report for July, August, and September 1952

Description: This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) effects of radiation on ice -- the x-ray induced luminescence of ice, (1.5) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (2.2) application of mass spectrometry to chemical problems, (2.3) vapor pressure and heat of vaporization of uraniu… more
Date: January 21, 1953
Creator: Gilbreath, J. R. & Simpson, O. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemistry Division, Section C-II, Summary Report for July, August, and September 1952

Description: This report deals with the (1.1) physical properties of graphite, (1.2) effects of pile irradiation on the properties of graphite, (1.3) effect of irradiation on "ceramic" materials, (1.4) effects of radiation on ice -- the x-ray induced luminescence of ice, (1.5) investigation of color centers and other optical properties of single crystals. (2.1) radiation chemistry of liquids, (2.2) application of mass spectrometry to chemical problems, (2.3) vapor pressure and heat of vaporization of uraniu… more
Date: January 21, 1953
Creator: Gilbreath, J. R. & Simpson, O. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Technical Review of ZPR-1 Accidental Transient - the Power Excursion, Exposures, and Clinical Data

Description: On June 2, 1952, 15:52 hours, a large reactivity change was made manually in a ZPR-1 assembly causing a power excursion of about one kwh, which resulted in damage to the reactor core components and radiation exposure of some of the operating personnel to perhaps several rep. None of the contributing causes is reviewed here nor are the measures which were taken to reduce the probability of a recurrence discussed since these are considered administrative matters beyond the scope of this technical… more
Date: January 26, 1953
Creator: Brittan, R. O.; Hasterlik, R. J.; Marinelli, L. D. & Thalgott, F. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Autoclave Testing of Mechanically Jacketed Thorium Slugs In Water

Description: Water corrosion tests on mechanically jacketed and pinholed thorium slugs show that these slugs fail in a manner similar to that observed for mechanically jacketed and tested uranium slugs. The proposed mechanism for the water corrosion of these jacketed slugs is analogous to the water corrosion mechanism of jacketed uranium slugs presented in the project lecture. A bare thorium slug appeared to be more resistant to corrosion by water than a mechanically jacketed slug during the first half of t… more
Date: January 29, 1953
Creator: Yaggee, Frank L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Summary Report October, November, and December, 1953

Description: Progress is reported on (1) experimental breeder reactor program, (2) solvent extraction, (3) fluoride volatilization separation process, (4) elevated temperature separations, (5) denitration of uranyl nitrate in a fluidized bed, (6) development of analytical techniques, (7) processing and utilization of radioactive wastes.
Date: January 1, 1954
Creator: Lawroski, Stephen & Stevenson, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Production Analysis - Graphical Method

Description: In the a study of plutonium production, the analytical solutions of the various isotope production equations are difficult and time consuming when spatial variation of the flux is considered. In an effort to reduce the time and labor required to determine the integrated production of a given thermal reactor, a graphical method of analysis is presented. The method is based on the assumption that the reactor may be divided into a relatively small number of regions such that the flux in each of th… more
Date: January 1954
Creator: Mumm, J. F. & Templin L. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Techniques for X-Ray Examinations of End-Weld Closures and Can-to-Cap Brazes on CP-6 Type Fuel Elements : Final Report -- Metallurgy Program 7.7.7

Description: A fuel element assembly in which a uranium slug is bonded to an impact extruded aluminum can by means of aluminum-silicon eutectic, and in which the can is capped with a thin aluminum disc, brazed and welded to the can, may contain,(a) imperfections common to brazed and welded metal sections, and (b) inhomogeneities arising from oxidation of uranium, and alloy formation between uranium, aluminum and silicon.
Date: January 20, 1954
Creator: Sidhu, S. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Process Equipment and Protective Enclosures Designed for the Fuel Fabrication Facility: Facility #350

Description: Report issued by the Argonne National Laboratory discussing the design and construction of equipment for reactor fuels. As stated in the summary, "the report describes the development, prototype construction, methods of testing, and leak detection of a modular hood design to be used in housing equipment and processes for the Argonne National Laboratory Fuel Fabrication Facility" (p. 9). This report includes tables, illustrations, and photographs.
Date: January 1956
Creator: Shuck, A. B. & Mayfield, R. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Argonaut Automatic Flux Controller Design Report

Description: Report issued by the Argonne National Laboratory over design studies conducted on Argonaut reactors for training and research purposes. As stated in the abstract, "the design presented in the form of a steady-state analysis based upon the small-signal linearization of the reactor kinetics transfer function. The measured controller performance and construction details of the equipment is given" (p. 7). This report includes tables, illustrations, and photographs.
Date: January 1960
Creator: Gerba, A., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Low Dead-Time Neutron-Counting-System

Description: From Abstract: "This report describes a counting system capable of processing input pulses at an average rate in excess of 3 x 10 to the fifth power counts per second with less than 10 percent counting loss due to instrumental dead time."
Date: January 1961
Creator: Epstein, Robert J. & Thompson, Donald C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Multicomponent Isotopic Separation and Recirculation Analysis

Description: A digital computer program for design of multi-component distillation columns has been developed based on an exact method of solution of the governing equations. Although this computer program was developed for enrichment of the spent fuels from presently conceived Tokamak-type fusion power reactors by cryogenic distillation, the program can be used for the design of any multi-component distillation column, provided, of course, the necessary thermodynamic and phase equilibrium data are availabl… more
Date: January 1976
Creator: Misra, B. & Maroni, V. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Unified and Mechanistic Approach to Creep-Fatigue Damage

Description: A new creep-fatigue equation is proposed that takes into account both plastic strain and strain rate. The coefficients and exponents in the damage-rate equation are interpreted by means of the various damage mechanisms of the material. The damage-rate equation has been integrated to analyze various phenomena such as the effects of plastic strain rate on monotonic tensile or creep rupture time, rising mean strain on the low-cycle fatigue behavior at elevated temperature, tensile and compressive … more
Date: January 1976
Creator: Majumdar, S. & Maiya, P. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Chemical Engineering Division Sodium Technology Annual Report: July 1975-June 1976

Description: The Sodium Technology program currently comprises three parts. The first part is aimed at developing a model for accurately describing the behavior of tritium in LMFBRs from its formation in the core to its ultimate retention in the cold traps or release to the environment. Two important parts of this model are the behavior of the sodium cold traps and permeation of tritium through the steam-generator heat-transfer surfaces. A tritium monitor has been developed and installed on EBR-II to measur… more
Date: January 1977
Creator: McPheeters, C. C.; Jardine, L. J.; McKee, J. M.; Raue, D. J.; Renner, T. A.; Skladzien, S. B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparisons of Finite-Element Code Calculations to Hydrostatically Loaded Subassembly-Duct Experiments

Description: The Liquid Metal Fast Breeder Reactor (LMFBR) core structure consists of a matrix of hexagonal subassembly ducts. Evaluation of the safety aspects of the core structure requires that reliable computational procedures be available to predict the deformation response of the subassembly configuration to postulated local energy releases. Finite-element computer codes have been developed to calculate deflections and strains of a hexcan subassembly wrapper subjected to internal and external dynamic p… more
Date: January 1977
Creator: Ash, J. E. & Marciniak, T. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Financial Overview of Integrated Community Energy Systems

Description: This report is designed to analyze the commercialization potential of various concepts of community-scale energy systems that have been termed Integrated Community Energy Systems (ICES). A case analysis of alternative ICES concepts applied to a major metropolitan development complex is documented. The intent of this study is twofold: (1) to develop a framework for comparing ICES technologies to conventional energy supply systems and (2) to identify potential problems in the commercialization of… more
Date: January 1977
Creator: Croke, K. G.; Hurter, Arthur P.; Lerner, E.; Breen, W. & Baum, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Generalized Parametric Model for Transient Gas Release and Swelling in Oxide Fuels

Description: The need for a capability to predict transient fission gas behavior arises because of the complexity of fission gas response to transient conditions, the importance of fission gas to fuel mechanical response, and the prevalent limitations on experimental information relevant to the problem. A detailed mechanistic analysis of intra-granular swelling and release of gas from grains to grain boundaries, both as they result from transient heating, has been developed and incorporated in a fission gas… more
Date: January 1977
Creator: Gruber, E. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigations of Materials Compatibility Relevant to the EBR-II System: Fiscal Year 1976

Description: Annual report on investigations of components of the EBR-II reactor plant and on out-of-reactor experiments in which materials or techniques are tested before they are used in the EBR-II reactor system. It includes a discussion of wide ranges of materials, circumstances, and evaluation techniques.
Date: January 1977
Creator: Longua, K. J.; Ruther, W. E.; Shields, J. A. & Clark, A. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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