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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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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 no… more
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 l… more
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 t… more
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 calcu… more
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 fu… more
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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Hanford Neptunium Oxalate-Oxide Process Experience

Description: In recent months, relatively large quantities of neptunium-237 have been recovered from Hanford irradiated uranium. The over-all recovery process consisted of 1) isolation from Purex plant solutions by solvent extraction, to yield an impure neptunium nitrate solution contaminated principally with uranium, plutonium, and fission products (2) purification by anion exchange 3) precipitation of neptunium (IV) oxalate; and 4) calcination of the oxalate to yield neptunium (IV) oxide, NpO2. This paper… more
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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