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Improved Zirconium Alloys : Summary Report, April 1, 1960 - January 31, 1961

Description: Abstract: "The objectives of this program are the development of zirconium-base alloys possessing exceptionally good corrosion resistance to 680 F water or 750-900 F system and/or improved strength at elevated temperatures. Approximately 100 binary compositions were prepared and screened by corrosion testing in 680 F water; selected compositions were exposed to 750 F steam. The data obtained indicate promising bases for ternary and quaternary alloys. Related investigations involving zirconium p… more
Date: February 28, 1961
Creator: Weinstein, Daniel; Holtz, F. C. & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department
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Improved Zirconium Alloys Quarterly Report: October - December 1960

Description: Quarterly report describing the progress and development of improved zirconium alloys for service in superheated water and steam. This report covers the period between October 1 to December 31, 1960 and was conducted by the United States and the European Atomic Energy Community (EURATOM).
Date: February 2, 1961
Creator: Weinstein, Daniel; Holtz, F. C. & Van Thyne, R. J.
Partner: UNT Libraries Government Documents Department
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The Boron-Carbon System: Quarterly Report Number 3, November 1960 - January 1961

Description: Abstract: A definitive investigation of the boron-carbon equilibrium system is being made by X-ray diffraction, metallographic, and thermal analytical techniques. On the basis of metallographic and X-ray diffraction studies it is concluded that boron carbide has a range of solubility from approximately 10 to 20 atomic per cent carbon at 1500 degrees to 2000 degrees Celsius. The melting point of the carbide-graphite eutectic has been established as 2325-2350 degrees Celsius. No reversible allotr… more
Date: February 6, 1961
Creator: Elliott, Rodney P.
Partner: UNT Libraries Government Documents Department
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Front shield weight and C. G.

Description: No Description Available.
Date: February 16, 1961
Creator: Phelps, E.
Partner: UNT Libraries Government Documents Department
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Hanford Laboratories Operation Monthly Activities Report: January 1961

Description: This is the monthly report for the Hanford Laboratories Operation, January 1961. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.
Date: February 15, 1961
Creator: Hanford Laboratories
Partner: UNT Libraries Government Documents Department
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Operation and Analysis of a 3000 KW Liquid Metal Model Steam Generator

Description: Abstract: A 3000 kw (thermal) bayonet duplex tube model steam generator was performance-tested in a liquid metal test loop at MSA Research Corporation, Callery, Pennsylvania, under the cognizance of Atomics International.
Date: February 28, 1961
Creator: Webster, L. J.
Partner: UNT Libraries Government Documents Department
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Artificial cooling of the Columbia River by dam regulation, 1960

Description: This report discusses benefits in an increase in the flow of water from the lower depths of the Grand Coulee Dam which was used to lower river temperature at HAPO. A net average daily reduction of over 1.2{degree}C resulted at HAPO with a peak of 2.7{degree}C. The Net Production gain from temperature change was 6910 MWD and the Cost of Control was: Grand Coulee Charges $3,120.00, and other (Estimated) 6,880.00 for a total of $10,00.00.
Date: February 15, 1961
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Design Modifications to the SRE during FY 1960

Description: Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Partner: UNT Libraries Government Documents Department
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LOLA - A Multi-Dimensional Optimization Code for the IBM 709-7090

Description: Report describing the LOLA computer code, which is "capable of processing analytical or empirical systems containing a large number of variable parameters" (p. 2). The report also describes the calculations that LOLA can make.
Date: February 1961
Creator: Egan, M. R. & Knudsen, C. N.
Partner: UNT Libraries Government Documents Department
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Initial Peak Surge Current Detection Circuits

Description: Test requirements for several components specifies that surge currents be monitored to determine if the initial peak surge current exceeds a certain predetermined amplitude. This report describes and evaluates two circuits which were developed by Organization 2451 to meet this requirement in production testing.
Date: February 1961
Creator: Conrad, Milo M.
Partner: UNT Libraries Government Documents Department
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Some fire and fission product release possibilities for discharged fuel slugs

Description: An attempt was made to appraise the slug fire and fission product possibilities associated with held-up slugs, as a function of slug power and down-time before discharge. Limitations of the data are discussed and suggestions given for refinement and related hazards analyses.
Date: February 7, 1961
Creator: Zima, G. E.
Partner: UNT Libraries Government Documents Department
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Revised requirements for continuous birch recovery at Redox

Description: The process criteria proposed use of the existing organic wash column, 10, as a stripping column for the neptunium accumulation and isolation cycles. It is now proposed to employ a new processing concept which will permit the use of the scrub section of the neptunium extraction column, 1S, for neptunium stripping thereby obviating the use of the 10 Column. This proposed new scheme will provide increased neptunium stripping efficiency and greater processing flexibility for the 1S Column. The rev… more
Date: February 2, 1961
Creator: Barnes, R. G.
Partner: UNT Libraries Government Documents Department
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Radiochemistry for the rupture of a Zircaloy-2 clad uranium fuel element in KER-1

Description: During the 0800--1600 shift on July 7, 1960, the delayed neutron monitor on KER Loop 1 indicated a high coolant activity level. Sympathetic responses were also recorded on the Loop 3 and Loop 4 instruments indicating a possible fuel element failure in Loop 1. The KE Reactor began shutdown operations immediately thereafter. The purpose of this report is to summarize the events pertinent to this reactor outage and to discuss the results obtained from coolant samples and a thermocouple wire sample… more
Date: February 28, 1961
Creator: Demmitt, T. F.
Partner: UNT Libraries Government Documents Department
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A standard AlSi braze wetting test for aluminum components used in the lead-dip process

Description: Wetting of the aluminum components by aluminum-silicon brazing alloy is a major factor influencing the quality of the fuel elements. Several process variables associated with the impact extrusion of aluminum components influence the resulting Al surface. In addition, these processing variables interact with the HAPO component production cleaning process to give varying results. Purpose of this document is to define the parameters for selecting, preparing) testing and evaluating the AlSi wetting… more
Date: February 1, 1961
Creator: Burgess, C. A.
Partner: UNT Libraries Government Documents Department
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Interim goal exposure plans for O-III-NB and O-III-EB material for B, D, DR and F reactors

Description: The purpose of this report is to recommend variable goal plans for natural and enriched bumper fuel elements, specifically for 0-III-NB and 0-III-EB materials, to be irradiated at the B, D, DR, and F Reactors. The average goal exposure for all bumper fuel elements at D Reactor was specified to be 900 MWD/T, with provisions being made for revision by normal procedures. Exposures for enriched bumper material at the B, M. and F Reactors were not specified in the PITA supplement authorizing chargin… more
Date: February 13, 1961
Creator: Bloomstrand, R. R.
Partner: UNT Libraries Government Documents Department
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Irradiated uranium fire hazard

Description: Earlier this year we briefly discussed the potential hazard of incurring an inadvertent uranium fuel element fire during discharge. This letter will provide data which will be of assistance to you in assessing the potential hazard, and in establishing charge-discharge procedures to minimize the probability of an irradiated fuel element lodged in the discharge area reaching aluminum jacket melting temperature without detection.
Date: February 16, 1961
Creator: Reid, R. W.
Partner: UNT Libraries Government Documents Department
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