Technical Report Archive & Image Library (TRAIL) - 19 Matching Results

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Description and Proposed Operation of the Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II)

Description: Report regarding "[t]he Fuel Cycle Facility for the Second Experimental Breeder Reactor (EBR-II), the process equipment, and the operations to be conducted in the facility are described. The Fuel Cycle Facility is a plant for reprocessing, by pyro-metallurgical methods, the core and blanket material discharged from EBR-II. The reactor core alloy is uranium-5 percent fissium and contains about 46 wt.% Uranium-235 . The blanket material consists of uranium in which plutonium is bred. Core and bla… more
Date: April 1963
Creator: Hesson, J. C.; Feldman, M. J. & Burris, L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Fabrication of UO2-Stainless Steel Dispersion Fuel For Borax-V Nuclear Superheat

Description: Report describing the development, fabrication, and nondestructive and destructive evaluation of stainless steel-clad fuel plates, the evaluation of fuel subassemblies, and the assembly of fuel element components at Argonne National Laboratory.
Date: December 1963
Creator: Kramer, W. C. & Bean, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Method of Calculating Transient Temperatures in a Multiregion, Axisymmetric, Cylindrical Configuration the Argus Program, 1089/Re248, Written in Fortran II

Description: From Abstract: "A detailed description is given of ARGUS, a FORTRAN II computer program for calculating transient temperatures in any concentric cylindrical configuration. Included are an explanation of the mathematical methods, a discussion of special features and restrictions, input and output descriptions, operating instructions, several sample problems, and the code listing."
Date: November 1963
Creator: Schoeberle, D. F.; Heestand, J.; Miller, L. B. & Miller, L. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Breeding-Gain Specimens for EBR-I Core IV

Description: Report issued by the Argonne National Laboratory over studies conducted on uranium and plutonium specimens used in fuel rods. The results are presented and discussed. This report includes tables, illustrations, and photographs.
Date: September 1963
Creator: Shuck, A. B.; Hins, A. G.; Burt, W. R. & Beatty, R. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Testing of Containment Capabilities of Reinforced Concrete-Shielded Enclosures

Description: From Summary: "The strains in the walls and ceiling of Cell No. 5 were recorded with 39 SR-4 strain gages strategically placed on reinforcing steel. Table I summarizes the comparative results without including correction for stress concentrations. The general pattern of cell behavior at 10 psig, as summarized in Table I, is shown in Figs. 10, 11, 12."
Date: March 1963
Creator: Fistedis, S. H.; Heineman, A. H. & Janicke, M. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Heat Transfer, Flow Instability, and Critical Heat Flux For Water in a Small Tube At 200 psia

Description: 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."
Date: June 1963
Creator: Weatherhead, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Performance Analysis of the EBWR at Various Power Levels

Description: From Introduction: "This study is an attempt to predict the operating performance of EBWR (Experimental Boiling Water Reactor) at various power levels. It was done at the same time that EWBR was raised in power up to 100 MW, and so an excellent possibility was given to check the validity of the used performance analysis. Rather than giving a general and complete outline of the analysis or establishing a new approach, the study outlines and specifies the numerous practical problems involved in … more
Date: October 1963
Creator: Nentwich, Alfred A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Development of an Electrical Resistivity Probe For Void-Fraction Measurements in Air-Water Flow

Description: "Work has been done on the adaptation of an electrical probe, developed by Neal for the measurement of local void fractions in mercury-nitrogen flow, to air-water flow. The adaptation is more difficult because of wetting of the probe by water. Various probe shapes and filming agents were employed without great success" (p. 1).
Date: June 1963
Creator: Nassos, George P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Practical Approach to Availability and Irreversibility

Description: From Introduction: "The purpose of this paper is to shed additional light on the techniques of a Second Law Analysis. The stimulus for writing this paper came from questions asked and difficulties that occurred during lectures on the subject at the graduate level. This paper utilizes Keenan's basic approach but presents the material with emphasis upon a clear definition of the work associated with each subsystem in the process."
Date: June 1963
Creator: Hoglund, Barton M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Two-Phase Critical Flow With Application to Liquid-Metal Systems (Mercury, Cesium, Rubidium, Potassium, Sodium, and Lithium)

Description: From Introduction: "In the present report the best available theory is utilized to calculate void fractions, slip ratios, and flow rates for liquid-vapor metal systems in pipes under critical flow conditions."
Date: October 1963
Creator: Fauske, Hans K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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An Experimental Investigation of Two-Phase, Two-Component Flow in a Horizontal, Converging-Diverging Nozzle

Description: Report that "describes an investigation of the flow characteristics in a horizontal, converging-diverging nozzle for a two-phase, two-component system" (p. 1) using air and water and "attempting to determine the effects of accelerating the liquid phase by the gaseous phase" (p. 1).
Date: July 1963
Creator: Vogrin, Joseph A., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report: March 1963

Description: 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.
Date: April 15, 1963
Creator: Adams, R. M. & Glassner, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactor Development Program Progress Report: April 1963

Description: 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.
Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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