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Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies

Description: Report describing a pilot plant constructed at Argonne National Laboratory for studying two major process steps for the recovery of uranium and plutonium from spent nuclear fuels of power reactors. A major objective is the demonstration of optimum process conditions for the two steps for synthetic reactor fuel compositions, including those containing mixtures of inactive fission products.
Date: 1964
Creator: Vogel, G. J.; Carls, E. L. & Mecham, W. J.
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Metallurgy Division Quarterly Report [for] October, November, and December 1955

Description: A total of nine clad plates, containing uranium -5 w/o zirconium 1.5 w/o niobium alloy cores and clad with Zircaloy-II, were rolled in plain carbon steel jackets, heat treated, physically evaluated, and corrosion tested. All these plates were found to be within predetermined dimensional tolerance in width, thickness, length, cladding thickness, and core distribution. Improved control of wielding variables and of the length of the seal pin projecting above the end plugs resulted in the eliminati… more
Date: June 1965
Creator: Foote, Frank G.; Schumar, James F. & Chiswik, Haim H.
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An Ultrasonic Measurement System for The Precise Determination of the Elastic Moduli of Single Crystals

Description: From Abstract: "The equipment described in this paper is based on the technique developed by McSkimin. Figure 1 shows a block diagram of the system. The oscilloscope presentation with no specimen present appears as shown in Figure 2a. At discrete frequencies, the pattern appears as shown in Figure 2b."
Date: May 1961
Creator: Renken, C. J.
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Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate

Description: From Introduction: "An experiment, designated MTR-W10, was designed to determine the effects of high burnup on the cladding and fuel of an aluminum-1% nickel alloy (M-388)-clad ceramic pellet-fuelded plate if the type manufactured at Argonne for the BORAX-IV core. Conditions of irradiation were selected to allow local boiling at the high flux end of the plate at a pressure of 600 psig."
Date: May 1960
Creator: Gavin, A. P.
open access

Interim Report: Faret Experimental Program

Description: From Introduction: "The Fast Reactor Test (FARET) program is part of the United States Fast Reactor Program directed toward the demonstration of breeder reactors essential to the long-range goal of utilizing fertile fuels. (1) With-in this program is the current thinking that the early construction and operation of two or three prototype nuclear power plants of the order of 250 Mw(e) will lead eventually to the construction of practical and economic full scale breeder reactors by the early 1980… more
Date: April 1963
Creator: Smaardyk, A.; Bump, T. R.; Handwerk, J. & Handwerk, J.
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Transient Behavior of a Natural-Circulation Loop Operating Near The Thermodynamic Critical Point

Description: From Introduction: "Interest in utilizing natural-circulation loops to obtain results that aid in the design of some boiler and nuclear reactor coolant systems has focused attention on the dynamic behavior of such loops. Much analytical and experimental work has been done so as to permit predictions of the transient behavior of both single-phase and two-phase neutral-circulation systems. The analytical portion of the study consisted of simulating the loop by utilizing a digital computer to pred… more
Date: May 1963
Creator: Harden, Darrel G.
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On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate

Description: From Introduction: "Specifically, we shall be concerned with the case of a solid right circular cylinder of infinite axial extent, having a stress-free outer boundary, being cooled by a temperature-independent boundary conductance, and having an axial heat-generation rate of form shown in Fig. 1. The inclusion of a radial dependence proportional to I^0(r/L) is only a minor complication in solving the required heat-transfer problem and, for reference, has been included in the solution for the te… more
Date: December 1966
Creator: Valentin, Richard A.
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Two-Phase Heat Transfer With Gas Injection Through A Porous Boundary Surface

Description: From Introduction: "The purpose of this study is to investigate some of the hydrodyamic aspects of two-phase heat transfer in the lower quality range. The results of this study should contribute to a better and more thorough understanding of the processes and mechanisms affecting two-phase heat transfer, and in this way help in improving its prediction."
Date: March 1964
Creator: Kudirka, A. A.
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Pictorial Studies of Molecules 1: Molecular Orbital Density Comparisons of H2, Li2, B2, C2, N2, O2, and F2

Description: From Review of Theory: " In practice, a very close approximation to the molecular orbitals can be obtained in this way. Recent calculations of this type, utilizing analysis and computer programs developed by the author, have resulted in the determination of the molecular orbitals for a large number of diatomic molecules in the form of Eq. (2). These functions, which are thought to be very close to the Hartree-Fock (i.e., the molecular orbitals demanded by theory) result, were used in the pictor… more
Date: July 1965
Creator: Wahl, Arnold C.
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XLIBIT: ANL Cross-section Library Code

Description: From Introduction: "With the acquisition by the Laboratory of a Control Data 3600 computer in the fall of 1963, a joint reprogramming project was undertaken by the Laboratory's Applied Mathematics Division and the Control Data Corporation to develop one - and two-dimensional diffusion-theory and Sn transport-theory programs for the CDC-3600. The XLIBIT code described in this report was developed as a part of this project. XLIBIT is a CDC-3600 program designed to: 1) Prepare a cross-section libr… more
Date: February 1966
Creator: Sparck, S. D.
open access

Reactor Development Program Progress Report: September 1966

Description: Report issued by the Argonne National Laboratory discussing progress made within the Reactor Development Program for September, 1966. The report includes highlights of the different project activities including plutonium utilization, fast breeder reactors, general reactor technology, advanced systems research, and nuclear safety. This report includes tables, illustrations, and photographs.
Date: October 26, 1966
Creator: Adams, R. M. & Glassner, A.
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