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Reactor Development Program Progress Report: March 1963
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Reactor Development Program Progress Report: April 1963
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Reactor Development Program Progress Report: November 1965
Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during November 1965. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Reactor Development Program Progress Report: May 1966
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.
Reactor Development Program Progress Report: September 1966
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.
Particle Accelerator Division Summary Report: April Through September 1960
Report issued by the Argonne National Laboratory discussing a summary report of the Particle Accelerator Division. As stated in the summary, "this report outlines two methods applicable respectively to longhand and computer calculations" (p. 4). This report includes tables, illustrations, and photographs.
Idaho Division Summary Report: July, August, September, 1960
Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.
Midwest Tandem Cyclotron: A Proposal for a Regional Accelerator Facility
Report issued by the Argonne National Laboratory discussing the proposal of the Midwest Tandem-Cyclotron accelerator facility. Descriptions of the facility designs, methods, and operations are presented. This report includes tables, illustrations, and photographs.
Design and Testing of a High-Heat Flux Electron-Bombardment Heater
Report issued by the Argonne National Laboratory discussing the testing of an electron-bombardment heater. As stated in the abstract, "the applications of electron-bombardment heating to liquid-metal heat transfer and reactor safety experiments are discussed. The design of a high-heat-flux, electron-bombardment heater (EBH) is presented" (p. 7). This report includes tables, illustrations, and photographs.
Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant
Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
Irradiation of an Aluminum Alloy-Clad, Aluminum-Uranium Alloy-Fueled Plate
Report issued by the Argonne National Laboratory discussing irradiation tests of an aluminum alloy-clad, aluminum-uranium alloy fuel plate. As stated in the introduction, "calculations were made to determine the lowest possible pressure which would allow the maximum possible local boiling on the plate and still assure a margin of safety against burnout" (p. 9). This report includes tables, illustrations, and photographs.
A Generalized Computer Program for Flowsheet Calculation and Process Data Reduction
Report issued by the Argonne National Laboratory discussing the PACER-65 computer program. As stated in the summary, the program "has been developed and utilized for flow sheet calculations and process-data reduction. PACER-65 is an executive program in which material- and energy-balance equations, conversion factors, etc., for each processing step are described by separate subroutines" (p. 5). This report includes tables, and illustrations.
Liquid MHD Power Cycle Studies
Report issued by the Argonne National Laboratory discussing the magnetohydrodynamics (MHD) power cycle for liquid metals. The benefits, and different phases of the MHD power cycle are presented. This report includes tables, and illustrations.
A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter
Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Self-Sustained Hydrodynamic Oscillations in a Natural Circulation Two-Phase-Flow Boiling Loop
Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
The Expulsion of Liquid from a Rapidly Heated Channel
Report documenting experiments in order to determine the "behavior of a partially confined liquid in contact with a rapidly heated surface" (p. 7). These liquids include water, methanol, ethylene bromide, and acetone.
Heat Transfer, Flow Instability, and Critical Heat Flux For Water in a Small Tube At 200 psia
From Abstract: Report discussing "the effects of developing two-phase flow regimes in a constant-pressure drop system are shown in recorded traces from a fast-response flow transducer: the mass velocity decreases and transfer-surface superheat increases with increasing steam quality."
An Ultrasonic Measurement System for The Precise Determination of the Elastic Moduli of Single Crystals
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."
Interim Report: Faret Experimental Program
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's. (2)"
Transient Behavior of a Natural-Circulation Loop Operating Near The Thermodynamic Critical Point
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 predict the measured transients."
Proceedings of the AMU-ANL Summer Study Program
From Introduction: "In 1954, the AEC presented the "five-year plan" for power reactor development, briefly outlined in Table I-1. The program proceeded and other reactors were added as a result of the incentives indicated in the outline."
Optimization of Efficiency of a Cesium Diode Converter
From Introduction: "The efficiency of the converter is computed with the least possible assumptions. Thermal emissivity and the interelectrode heat-transfer coefficient are varied, and the effect on efficiency is investigated."
Two-Phase Heat Transfer With Gas Injection Through A Porous Boundary Surface
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."
Pictorial Studies of Molecules 1: Molecular Orbital Density Comparisons of H2, Li2, B2, C2, N2, O2, and F2
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 pictorial calculations presented in this report."
XLIBIT: ANL Cross-section Library Code
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 library tape. 2) Modify an existing cross-section library tape. 3) Duplicate an existing cross-section library tape. 4) Print all or a portion of the cross-section data on the library tape. Punch cross-section decks for all or a portion of the data on the library tape. The decks produced are identical to those used in pertaining the tape."
Irradiation of an Aluminum Alloy-Clad Ceramic Pellet-Fueled Plate
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."
A Report on Some Attempts to Case Centrifugally Fuel Elements of Small Diameter
From Abstract: "The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated."
On The Steady-State Thermal Stresses in Cylindrical Fuel Pins Due to Axial Variations in Their Internal Heat-Generation Rate
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 temperature field to be found in Section II below."
A Study of Convective Magnetohydrodynamic Channel Flow
Analysis of a class of steady magnetohydrodynamic channel flow problems when natural, as well as forced, convection is important.
Condensation of Metal Vapors: Mercury and the Kinetic Theory of Condensation
Report issued by the Argonne National Laboratory discussing condensation theories of metal vapors. As stated in the introduction, "the objectives of this research then are critical analysis of condensation theories and data for metal vapors and experimental evaluation of the resistance to condensation for a representative metal such as mercury" (p. 18). This report includes tables, illustrations, and photographs.
Performance Characteristics of a Liquid Metal MHD Generator
Report issued by the Argonne National Laboratory discussing the performance of magnetohydrodynamic generators. As stated in the abstract, "an experimental study was made of the performance characteristics of a liquid metal MHD generator utilizing single-phase sodium-potassium and two-phase sodium-potassium-nitrogen fluids. The purpose of this study was to compare the generator performance with theory for single-phase flow and to determine the effects of the introduction of the gaseous phase on the generator output and efficiency" (p. 9). This report includes tables, illustrations, and photographs.
A Hybrid-Computer Program for Transient Temperature Calculations on TREAT Fast Reactor Safety Experiments
Report issued by the Argonne National Laboratory discussing a computer program used for fast reactor safety experiments. As stated in the summary, "this report gives a detailed description of a hybrid-computer program for calculating temperatures in a multi-region, axisymmetric, cylindrical configuration consisting of solid materials bounded by flowing coolant. Included is an explanation of the mathematical methods, together with a discussion of special features, input-output descriptions, and several sample problems" (p. 7). This report includes tables, and illustrations.
Spectral Representation and Criticality Problem of a Two-Region Cell Transport Operator
Report determining the solution of the transport equation to determine accurate conditions for the criticality of a two-region fuel-moderator assembly with reflecting boundaries.
Flow-Regime Transitions at Elevated Pressures in Vertical Two-Phase Flow
Two-phase flow-regime transitions at elevated pressures for a single-component, trichloromonofluoromethane, were investigated for forced-circulation, upward flow in a vertical, rectangular conduit with internal dimensions of 0.380 by 1.050 inches.
Idaho Division Summary Report
Report issued by the Argonne National Laboratory discussing a summary of projects conducted with the Idaho Division. Descriptions of each project are presented. This report includes tables, and illustrations.
Engineering Development of Fluid-Bed Fluoride Volatility Processes: Part 5. Description of a Pilot-Scale Facility for Uranium Dioxide-Plutonium Dioxide Processing Studies
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.