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Positional Tolerancing at Sandia Corporation

Description: The positional tolerance method of dimensioning is described. The emphasis is placed on the elimination of ambiguities and increase in tolerances provided by this method as compared to the older, bilateral method. (auth)
Date: May 1, 1959
Creator: Eichert, F. F. & Nicovich, P. A.
Partner: UNT Libraries Government Documents Department
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An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building

Description: Abstract: "An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fallout. Pocket ionization chambers were used for measurement of the radiation-field strength. Fallout was simulated with distributed and point-source configurations of Co-60 and Ir-192 sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exp… more
Date: May 1, 1959
Creator: Batter, J. F., Jr.; Kaplan, A. L. & Clarke, Eric Thacher
Partner: UNT Libraries Government Documents Department
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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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Hanford Laboratories Operation monthly activities report, April 1959

Description: This is the monthly report for the Hanford Laboratories Operation, April, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities. Biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation programming, radiation protection, and laboratory auxiliaries operation are discussed.
Date: May 15, 1959
Partner: UNT Libraries Government Documents Department
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Production test IP-255-A-9-FP E-N demonstration test

Description: The objectives of the test described in this report are to evaluate the integrity of I & E MINT fuel elements canned by the ``C`` process to determine the conversion ratio of I & E geometry E-N ``striped loadings,`` and to provide a demonstration loading for a full reactor loading incorporating a ``striped`` center loading and a fringe ``blanket`` loading. This test will involve two portions a 26 tube block loading of I & E enriched uranium and MINT fuel elements arranged in a striped array, an… more
Date: May 8, 1959
Creator: Hall, R. E. & Nechodom, W. S.
Partner: UNT Libraries Government Documents Department
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Historical record of data on flood control

Description: Last year (1948) during the flood period the flow at Grand Coulee fluctuated widely. 2 PM, June 8, 543000 c.f.s.; 4 AM, June 9, 568000 c.f s.; 2 PM, June 9, 543000 c.f.s.; 2 AM, June 10, 573000 c.f.s. A total instantaneous fluctuations of 37,500 c.f.s. was reported. Now there is installed a new control. This control can keep downstream variation within 500 c.f.s. By lowering the lake level prior to the crest period, the drum gates could be used as flood control (1948 high water basis) the drum … more
Date: May 19, 1959
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Radiation decay data of various dummies and aluminums

Description: Sections of the dummies furnished by Radiological Engineering, Process Reactor Development Operation were machined into 1/4 inch diameter by 1 inch long cylinders and irradiated in the Quickie Facility at F area. The pieces were discharged directly into a holder one foot from the Beckman chamber. The transient time from in-pile to the chamber is approximately 30 seconds. The readings were taken using a Beckman chamber, Beckman Micro-Micro Ammeter and Recorder. This system has been calibrated wi… more
Date: May 27, 1959
Creator: DeMers, A. E. & Olson, W. B.
Partner: UNT Libraries Government Documents Department
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Physics and Instrument Research and Development Operation. Monthly report, April 1959

Description: Areas covered in this report are as follows: nuclear safety in the Fuel Preparation Dept.; studies related to the present production reactors; studies related to future production reactors; studies related to separation plants; studies form the neutron cross section program; reactor development (gas cooled reactor program and test reactor operations); and biology and medicine.
Date: May 12, 1959
Creator: Gast, P. F.
Partner: UNT Libraries Government Documents Department
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Artificial cooling of the Columbia River by dam regulation: Part 1

Description: In early July 1958, it appeared that Columbia River temperatures at HAPO would be near 24--50{degree}C by the end of August. River temperatures were averaging 40 to 50{degree}C above 1957 figures and were 3{degree} to 4{degree} above the ten year highs. It seemed desirable to examine the problem to determine if any corrective measure could be taken, since it was apparent that production losses were imminent. The large storage of cold water behind Grand Coulee Dam, normally untapped, was a sourc… more
Date: May 25, 1959
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Increased production from deliberate discharge cycling

Description: Considerable production gains might be attained if each reactor discharged its entire flattened region during one scheduled outage instead of utilizing several outages for this purpose. Several of the older reactors are now discharging a high percentage of their flattened zones in a single outage and could be put into this type of operation with relatively little difficulty. Production gains may be possible through better flattening efficiency, a more favorable rupture rate effect, fewer non-eq… more
Date: May 28, 1959
Creator: Carter, R. D.
Partner: UNT Libraries Government Documents Department
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Chemical Processing Department monthly report, April 1959

Description: Production of Pu from separations plants was only 58% of April commitment because of Purex difficulties. UO{sub 3} production, shipments met schedules. Pu shape production and shipments exceeded forecast by 14%. Purex HS column, repaired Oct 1958, developed another leak and was bypassed April 18, resulting in Pu and U that required reprocessing. A Palm recovery run at Purex with all- reducing flowsheet, resulted in 87% recovery and excellent decontamination of product. The prototype dual-pass s… more
Date: May 21, 1959
Partner: UNT Libraries Government Documents Department
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Maritime Organic Moderated and Cooled Reactor

Description: Introduction: This document describes the results of a six-week conceptual design study of an organic moderated and cooled reactor (OMCR) power plant adapted to a Class T-7 tanker.
Date: May 27, 1959
Partner: UNT Libraries Government Documents Department
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Positional Tolerancing at Sandia Corporation

Description: Abstract: "This brochure presents a brief introduction to the Positional Tolerance Method of DImensioning as employed by Sandia Corporation. The emphasis is placed on the elimination of ambiguities and increase in tolerances provided by this method as compared to the older, bilateral method."
Date: May 1959
Creator: Sandia Corporation. Design Definition Department.
Partner: UNT Libraries Government Documents Department
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Analysis of 100-K emergency water requirements after CGI-844 pump failure

Description: The demand plot has a 5-set, modified pump decay curve; it shows that 20,000 gpm emergency flow would be required within 80 seconds of complete pump power failure. Bases for the demand curve are constant bulk inlet temperature of 2 C, constant bulk outlet temperature of 95 C, K-3 I&E fuel elements, and initial reactor flow of 188,000 gpm.
Date: May 28, 1959
Creator: Corlett, R. F.
Partner: UNT Libraries Government Documents Department
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Artificial cooling of the Columbia River by dam regulation. Part 3

Description: The temperatures of the Columbia River was reduced 1 to 30 Centigrade with beneficial effects at HAPO. It is reasonable to expect that future benefits may be possible. It is desirable that the temperature of the river be controlled each year to the maximum extent possible. Instrumentation improvements requested to effect optimum savings. Records of river temperatures and flows should continue to be maintained by IPD as a necessary part of temperature optimization. Where possible, the coincident… more
Date: May 25, 1959
Creator: Kramer, H. A.
Partner: UNT Libraries Government Documents Department
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Irradiation performance of coextruded enriched uranium fuel rod PT-IP-A172-A: Final report

Description: The proposed operating conditions for fuel elements to be charged into the NPR require the fuel to be of an extended surface geometry and maintain adequate strength and corrosion resistance in 300 C water. A contract was let to Nuclear Metals Inc. to produce by co-extrusion lengths of fuel rod containing both natural and 1.6% enriched uranium of irradiation quality for fabrication into fuel elements. The fuel rods used in the irradiation test represent the first enriched uranium rods coextruded… more
Date: May 26, 1959
Creator: Claudson, T. T.
Partner: UNT Libraries Government Documents Department
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