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Niobium Phase Diagrams : Manuscript Report on Niobium-Carbon System

Description: Abstract: "The niobium-carbon system has been determined by X-ray and metallographic examination of sintered and arc-cast alloys. Two carbides exist: hexagonal Nb2C with a limited range of homogeneity, and cubic NbC with a solubility range from 8.25 to 10.25 weight per cent carbon. Dilute alloys freeze by eutectic reaction at 2230 C. The solubility of carbon in niobium is 0.80 at the eutectic temperature, but this decreases rapidly with temperature. Metallographic evidence indicates a peritecti… more
Date: May 6, 1959
Creator: Elliott, Rodney P.
Partner: UNT Libraries Government Documents Department
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Definitive process design, Redox multi-purpose dissolver installation

Description: This document provides the required definitive scope design for dissolver equipment capable of nuclear safe processing by geometry of E-Metal and certain other fuels enriched to a maximum of one per cent U-235 equivalent. Using only a single dissolver installation of this design, it will be possible to process the current E-Metal monthly commitment in less than two weeks (five-day week). The proposed dissolver system is to incorporate design flexibility required to permit conversion to Zirflex … more
Date: May 6, 1959
Creator: Gustafson, L. D.
Partner: UNT Libraries Government Documents Department
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Irradiation summary -- PT-IP-179-A-97-FP: Evaluation of the effect of a modified Beta-Heat treatment cycle on dimensional stability of uranium fuel elements

Description: The air quench prior to water quench during core heat treatment can be used to control slug distortion. In August 1959, a production test authorized the charging of 16 tubes of 43-second air quench material alternated with standard control material in C-Reactor. The test was charged on November 24, 1958, and discharged on April 26, 1959. This report summarizes and evaluates the irradiation performance of the material.
Date: August 6, 1959
Creator: Peacock, D. W. & Hall, R. E.
Partner: UNT Libraries Government Documents Department
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Fringe isotope production

Description: The Purpose of the work described in this report has been to determine experimentally the rate of production of tritiun in fringe lithium-aluminum alloy loadings with the degree of precision necessary for economic analyses of such a method of isotope production. These results are provided for use in such an analysis.
Date: May 6, 1959
Creator: Bunch, W. L.
Partner: UNT Libraries Government Documents Department
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A Large Bakeable Vacuum Valve

Description: This report describes the development and design of a large bakeable valve that is based on a unique seat arrangement and a novel motion seal.
Date: August 6, 1959
Creator: Batzer, Thomas H.
Partner: UNT Libraries Government Documents Department
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The Use of Boron for Fluoride Complexing in Thorex Dissolver Solutions

Description: Preliminary measurements of the corrosion of titanium were made in 13 M HNO3-0.05 M fluoride using 0.1 M H3BO3 as a liquid and vapor phase complexing agent. Titanium Ax-55 was attacked at average rates of 0.58 and 0.33 mils/month in the liquid and vapor. In dissolver solutions containing 0.5 and 1.0 M titanium, all rates were less than 0.1 mils/month.
Date: August 6, 1959
Creator: Kitts, F. G.
Partner: UNT Libraries Government Documents Department
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Confinement System Instrumentation

Description: Instrumentation shall be provided as shown on the attached drawing, SK-1-26835 for Confinement System Control. The Primary objective of the confinement system shall be to provide maximum possible confinement of contamination, consistent with building limitations, in the event of any contamination, consistent with building limitations, in the event of any credible reactor accident resulting from equipment failure or reactor mis operation.
Date: November 6, 1959
Creator: Richards, W. A.
Partner: UNT Libraries Government Documents Department
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Flow Decay After an Electrical Power Outage in the PRTR

Description: Previously, W. S. Figg and T. W. Ambrose (HW-51767 Rev) have investigated the problem of flow decay following electrical power loss to the PRTR primary coolant pumps. However, since the time of their study many reactor piping changes have been made in the design; therefore, it has become advisable to re-examine the problem incorporating these changes.
Date: February 6, 1959
Creator: Muraoka, J.
Partner: UNT Libraries Government Documents Department
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Specification for Requisition G-3855923Xircalogy-4 Jacket Tubing

Description: This specification is specifically designed for the procurement of Zircaloy tubing to be used in the of swaged, UO fuel elements, an, and the Pu fuel elements for the Plutonium Recycle Test Reactor. Requisition G-385923 contains the following information pertinent to this specification: 1. Dimensions and dimensional tolerance. 2. Source of zirconium sponge and conditions for us of Zircaloy scrap. 3. Inspection requirements. 4. Shipping instructions.
Date: November 6, 1959
Creator: Oakes, H. P.
Partner: UNT Libraries Government Documents Department
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PRTR Hazard Analysis For Various Mechanical Failures

Description: The hazards associated with several possible mechanical failures were analyzed for the PRTR. The consequences of these failures were evaluated for inclusion in the Final Hazards Summary Report.
Date: July 6, 1959
Creator: Muraoka, J.
Partner: UNT Libraries Government Documents Department
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Amendment No. 4 to Hazards Summary Report For The Dresden Nuclear Power Station

Description: This report is an amendment to the Preliminary Hazards Summary Report (1) and the Operating Procedures and Emergency Plans (5) for the Dresden Nuclear Power Station, submitted to the United States Atomic Energy Commission on September 3, 1957, and June 5, 1958, respectively.
Date: February 6, 1959
Creator: Commonwealth Edison Company
Partner: UNT Libraries Government Documents Department
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Flame Photometric Determination of Iron Parts I, II, III and IV

Description: A study was made of a method for the flame photometric determination of iron. In Part I of this report, the flame emission spectrum of iron, measured by means of a Beckman Model DU spectrophotometer with a flame attachment, is compated to that measured with an ORNL high-sensitivity, recording, single-beam instrument, in order to determine which instrument is best suited for this application. Although it was found that the Beckman product has the higher resolving power over the wavelength region… more
Date: May 6, 1959
Creator: Menis, Oscar
Partner: UNT Libraries Government Documents Department
open access

Dynamic Response of Reactor Plant to Load Changes. Section I. First Performance. Core I, Seed 1. Test Results DL-S-251 (T-612390)

Description: The purpose of the test was to determine the responses of the plant when subjected to load transients exceeding the design magnitudes, and to determine the maximum load changes, positive or negative, that the plant can sustain. The reactor plant responded satisfactorily to all load transients. The only limits exceed were the pressurizer high and low level alarm points. The magnitude of the transients and the time required for the plant to return to equilibrium was dependent upon the size of the… more
Date: November 6, 1959
Creator: Gentry, George
Partner: UNT Libraries Government Documents Department
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