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Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report

Description: From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Partner: UNT Libraries Government Documents Department
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Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant

Description: "This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Partner: UNT Libraries Government Documents Department
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ANNUAL REPORT

Description: The national laboratory concept, laboratory objectives, the staff, research facilities. research activities, and administration are discussed in general terms and a financial statement is given. Fairly detailed accounts are given for the research programs in the fields of physics, accelerator development, instrumentation, applied mathematics, chemistry, nuclear engineering, biology, and medicine. (W.D.M.)
Date: July 1, 1959
Partner: UNT Libraries Government Documents Department
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An Application of Spencer's Method to the Stieltjes and Hamburger Moment Problems

Description: Given the moments of a function it is often desirable to obtain a numerical approximation of the function. A method for estimating the solutions of the Stieltjes and Hamburger moment problems is developed. Calculations indicate that the method is both feasible and accurate. (auth)
Date: July 1, 1959
Creator: Guilinger, W. H.
Partner: UNT Libraries Government Documents Department
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Boiling Water Reactor Study [Part 1]: 306 Mw Power Reactor Conceptual Design

Description: From introduction: In general, the objective of this study is to provide for the development of the conceptual design criteria for the most promising type of boiling water reactor and associated complete electrical generating plant consistent with a schedule calling for start of construction in July 1960.
Date: July 1959
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
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Boiling Water Reactor Study [Part 2]: Separate Studies

Description: From introduction: This section presents the principal results of the optimization study done to establish the economic basis for selection of the core and fuel design.
Date: July 1959
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
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Boiling Water Reactor Study [Part 3]: 306 Mw Coal-Fired Installation

Description: From introduction: The objectives of this study are to determine the estimated capital and energy costs of this typical conventional coal-fired installation, consistent with a schedule calling for completion of construction April 1964.
Date: July 1959
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
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The Chattanooga Shale of Tennessee as a Source of Uranium: Final Report

Description: From major objective: The over-all aim of the study has been to obtain a thorough geologic picture of the Chattanooga shale in the area under consideration, with emphasis upon stratigraphic relationships and associated special problems from which, in turn, implications may be obtained as to the origin and age of the formation and possibly the source of the uranium. The study has not been aimed primarily at exploration for uranium and its economic aspects.
Date: July 1, 1959
Creator: Stockdale, Paris B. & Klepser, Harry J.
Partner: UNT Libraries Government Documents Department
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COMPATIBILITY OF ZIRCONIUM HYDRIDE AND CARBON DIOXIDE

Description: The stability of unclad zirconium hydride was investigated as a reactor moderator in carbon dioxide coolant. Two ranges of hydride were tested, an alpha- plus deltaphase hydride (ZrH/sub 0.9 plus or minus 0.2/) and a delta-phase hydride (ZrH/sub 1.5/). The delta-phase hydride exhibited excellent dimensional stability, but suffered as great as 20% hydrogen loss at 1200 deg F, together with severe corrosion. The alphaplus delta-phase hydride swelled and warped in a temperature gradient but did not lose much hydrogen and did not corrode severely even at 1200 deg F. The results indicate that zirconium hydride could not be used as unclad moderator in a carbon dioxide atmosphere in the temperature range desired for the Maritime Gas Cooled Reactor. (auth)
Date: July 1, 1959
Creator: Shoemaker, H.E.
Partner: UNT Libraries Government Documents Department
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Core-Temperature Excursions Following a Piping Failure in the Plutonium Recycle Test Reactor

Description: An evaluation of the temperature excursion and its possible consequences arising from loss of coolant from the Plutonium Recycle Test Reactor (PRTR) was made for four different postulated ruptures in the primary heavy water coolant system. As a basis for the evaluation, a series of computations was made. These were based on incremental heat and mass balances for sections of Zircaloy-clad UO/ sub 2/and Pu- Al fuel elements. Solutions to each problem defined by the postulated break size and its location were defined by finitedifference approximatioms performed by an IBM 653 machine digital computer. The four postulated ruptures were: (1) a complete parting of the 14-in.-diameter outlet pipe near the upper ring header so that coolant would be lost from both broken ends; (2) a rapture equivalent to a 14-in.-diameter hole in the primaryloop piping adjacent to the upper ring header; (1) a complete parting of a 1 3/4-in. upper jumper; and (4) a complete parting of a 1 3/4-in. bottom jumper. The Pu-Al elements represent the most critical component; melting of these elements would begin about 219 seconds after the rapture occurred if emergency backup light water coolant were not available to the system. It was found that the injection of 750 gallons per minute (gpm) of emergency coolant (375 gpm to each ring header) would be adequate to prevent melting or failure of any reactor component for all cases studied even if injection did not begin until 2 or 3 min alter the rupture occurred. An earlier injection time would, of course, be beneficial. (auth)
Date: July 1, 1959
Creator: Lemmon, A. W., (Jr.); Alexander, C. A.; Hulbert, L. E. & Filbert, R. B., (Jr.)
Partner: UNT Libraries Government Documents Department
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Electron-Population Analysis and the Dipole Moment of the LiH ¹Σ⁺ Excited State / A.M. Karo

Description: Abstract: "Detailed consideration is given to some properties of the first excited electronic state. Following the analysis proposed bv Mulliken, SCF LCAO-MO coefficients are used to obtain qualitative information about the electron distributions. Comparison is made with earlier work with respect to the description of the excited-state dipole moment, the effective electric moment between the ground and excited states is also calculated. From this, the oscillator strength for the first allowed transition is computed as a function of the internuclear distance."
Date: July 1959
Creator: Karo, Arnold M.
Partner: UNT Libraries Government Documents Department
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ELECTRON-POPULATION ANALYSIS AND THE DIPOLE MOMENT OF THE LiH$sup 1$$Sigma$$sup +$ EXCITED STATE

Description: Detailed consideration is given to some properties of the first excited electronic state. Following the analysis proposed by Mulliken, SCF LCAO-MO coefficients are used to obtain qualitative information about the electron distribution. Comparison is made with earlier work with respect to the description of the excited state in terms of the interacting configurations. In addition to the excited-state dipole moment, the effective electric moment between the ground and excited states is also calculated. From this, the oscillator strength for the first allowed transition is computed as a function of the internuclear distance. (auth)
Date: July 1, 1959
Creator: Karo, A.M.
Partner: UNT Libraries Government Documents Department
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GENERALIZED FUNCTIONS OF GREEN FOR SYSTEMS OF ORDINARY DIFFERENTIAL EQUATIONS

Description: The adjoint operator of a matrix operator and adjoint boundary conditions for adjoint matrix operators are defined. It is shown that a matrix operator can be associated in various ways with a scalar differential operator and if two adjoint matrix operators are associated with scalar differential operators then the scalar operators are adjoint. Generalized Green's functions are obtained and their use for solving boundary-value problems is discussed. Properties which characterize a generalized function of Green are obtained and it is shown that the generalized functions of Green of adjoint boundary-value problems are adjoint kernel matrices. Generalized Green's functions for scalar boundaryvalue problems are discussed and special cases taken up. (C.J.G.)
Date: July 1, 1959
Creator: Wyler, O.
Partner: UNT Libraries Government Documents Department
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"Granite" Exploration Hole, Area 15, Nevada Test Site, Nye County, Nevada -- Interim Report: Part A, Structural, Petrographic, and Chemical Data

Description: From introduction: The "Granite" exploration hole was core drilled to determine the character of the igneous rocks from the surface to a depth of 1,200 feet and the degree of structural anisotropism of the rock within 200 feet of a point 950 feet below the surface. This report summarizes the data on the structure, chemistry, petrology and alteration of the rocks exposed at the surface in the immediate vicinity of the drill site and in the core.
Date: July 1959
Creator: Houser, F. N. & Poole, F. G.
Partner: UNT Libraries Government Documents Department
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Hanford Neptunium Oxalate-Oxide Process Experience

Description: The over-all recovery process consisted of isolation from Purex plant solutions by solvent extraction, to yield an impure neptunium nitrate solution contaminated principally with U, Pu, and fission prcducts; purification by anion exchange; precipitation of nepturium(IV) oxalate; and calcination of the oxalate to yield NpO/sub 2/. The oxalate precipitation process investigations and results are described. (W.L.H.)
Date: July 1, 1959
Creator: Pollock, C. W. & Schneider, R. A.
Partner: UNT Libraries Government Documents Department
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HIGH-TEMPERATURE WATER AND STEAM-CORROSION BEHAVIOR OF ZIRCONIUM-URANIUM ALLOYS

Description: Weight change vs. time curves expressing the corrosion behavior of zirconium alloys containing additions of 10 through 60 wt.% uranium tested in 600 and 680 F water and in 750 F steam at 1500 psi are presented. The effects of various heat treatments on the subsequent corrosion properties are also included. (auth)
Date: July 1, 1959
Creator: Kass, S.
Partner: UNT Libraries Government Documents Department
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Hydrologic and Tracer Studies in Mohawk River at Knolls Atomic Power Laboratory

Description: Preface: In 1948, the U.S. Geological Survey, in cooperation with the Atomic Energy Commission, initiated a study of the hydraulics and hydrology of Mohawk River in the vicinity of the Knolls Atomic Power Laboratory (KAPL) near Schenectady, N.Y. The purpose of this study was to determine the probable effects of release of low concentrations of radioactive wastes from the Laboratory to Mohawk River.
Date: July 1959
Creator: Simpson, Eugene Sidney; Beetem, W. A. & Ruggles, F. H., Jr.
Partner: UNT Libraries Government Documents Department
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INFORMATION, COMMUNICATION, AND LANGUAGE

Description: A lecture delivered at Sandia Corp., Albuquerque, N. Mex., June 18, 1958. A discussion of information exchange theory is presented. Semantics in communications are examined, and the use of symbols in thinking and presentaion are discussed in some detail. (J.R.D.)
Date: July 1, 1959
Creator: Hammer, P.C.
Partner: UNT Libraries Government Documents Department
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