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Nuclear Parameter Survey of Molybdenum-Uranium Alloy Fuels for the Sheldon Reactor

Description: A parameter survey was conducted on 19-rod fuel clusters using 3 and 10 wt.% Mo--U alloys. Graphs are included for the core diameter and initial conversion ratio for k/sub eff/= 1.064 as a function of moderator can size, and for the effect of the Mo resonance integral. (D. L.C.)
Date: March 28, 1958
Creator: Blaine, R. A.
Partner: UNT Libraries Government Documents Department
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Creep Strength of Uranium Alloys at 1500 and 1800 F

Description: Abstract:"The creep resistance of various uranium binary alloys was investigated at 1500 and 1800 F in vacuum. Tests were made on alloys of uranium with beryllium, columbium, molybdenum, tantalum, titanium, and zirconium and on molybdenum-UO2 composites. Of the alloys examined, those of the uranium-molybdenum system exhibited the best creep resistance. At 1500 F, creep rates of about 0.005%/hr were produced in uranium-molybdenum alloys by a stress of 2500 psi and, at 1800 F, similar creep rates… more
Date: May 28, 1953
Creator: Saller, Henry A.; Stacy, J. T.; Eddy, N. S. & Klebanow, H. L.
Partner: UNT Libraries Government Documents Department
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Development of Methods for End Capping PWR Fuel Elements

Description: The following report discusses the development of methods for sealing the ends of metallic-cored fuel rods.
Date: December 28, 1955
Creator: Vagi, J. J. & Martin, D. C.
Partner: UNT Libraries Government Documents Department
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The Stability and Existence Range of the Zirconium-Uranium Epsilon Phase

Description: Report discussing studies regarding properties of the zirconium-uranium epsilon phase related to stability and existence range. Data showing this phase's thermodynamic stability is presented as well as the zirconium-uranium constitutional diagram. Oxygen and nitrogen effects on zirconium-uranium alloys and epsilon-phase alloys is included as well as ternary zirconium-uranium-oxygen diagrams.
Date: May 28, 1956
Creator: Rough, Frank A.; Austin, Alfred E.; Bauer, Arthur A. & Doig, J. Robert
Partner: UNT Libraries Government Documents Department
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Differential Thermal Analysis of Uranium Tetrafluoride-Uranium Dioxide Mixtures

Description: Abstract: "Approximate melting points have been determined for five samples of uranium tetrafluoride representing incompletely converted uranium dioxide and covering the range from about 2 to 20 w/o UO2, using the method of differential thermal analysis. The results indicate the melting temperatures are in the range of 920 to 980 C. No significant correlation between melting point and UO2 content was observed, possibly because of calcite formation. Similar results were obtained on synthetic mis… more
Date: June 28, 1956
Creator: Ewing, Robert A. & Bearse, Arthur E.
Partner: UNT Libraries Government Documents Department
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Radiological sciences department investigation: Radiation incident class I, No. 608-C

Description: At about 6:30 a.m. one of the two Process Operators regularly stationed at 233-S was performing routine work in the Control Room, heard a nearby Poppy alpha detector breaking down.'' He checked and found the instrument appeared to be in operating condition as it would respond to a high level source. Further checking indicated that he was contaminated and that nearby horizontal surfaces were contaminated. This information was phoned to the Shift Supervisor who told the Operator that he would be … more
Date: June 28, 1956
Creator: Vanderbeek, J.W.
Partner: UNT Libraries Government Documents Department
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Massachussetts Institute of Technology progress report

Description: This is the thirty-sixth progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress during the period of November 30, 1954 through February 28, 1955 is reported.
Date: February 28, 1955
Partner: UNT Libraries Government Documents Department
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Report on decreasing available acceleration of 190-B process pump turbines in order to reduce emergency steam demand

Description: As originally installed, the primary process pump turbines in 190-B were arranged to accelerate considerably upon loss of BPA electric power supply to the Process Pump House. However, the acceleration comes too late to be of value in maintaining top of riser pressure within the first second or two, and the acceleration results only in maintaining final process water pressure and flow at values higher than needed. It is desired to limit the acceleration of the turbines to a relatively small amou… more
Date: December 28, 1951
Partner: UNT Libraries Government Documents Department
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High Pressure Low Resistance Joint

Description: The following report describes the usage of tin-foil to obtain a mechanical joint of low electrical resistance while providing a seal to hold water at a pressure of 300 psi.
Date: March 28, 1955
Creator: Peters, Ralph
Partner: UNT Libraries Government Documents Department
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Reflection of Electrons by a Model Magnetic Mirror Machine

Description: Abstract: A visualized electron beam has been reflected by a conventional magnetic mirror. Visualization of the beam path from the electron gun to and including the region of reflection was achieved by the "thread ray" technique of Wehnelt. The total current passing through a magnetic mirror has been measured as a function of the beam energy and angular momentum for H₂ over a range of pressures from 0.5 to 5 microns.
Date: May 28, 1954
Creator: Ford, Franklin C.
Partner: UNT Libraries Government Documents Department
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A Noble Gas Scintillation Counter

Description: The following report describes a gaseous scintillation counting system, including the production and operation of the counter.
Date: May 28, 1957
Creator: Dickieson, Robert W.
Partner: UNT Libraries Government Documents Department
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Capacity survey -- Separations Division

Description: Recent tentative production forecasts indicate that as much as 96.6 Kg plutonium, associated with 190 tons uranium, may be produced each month. The ability of the Separations facilities to process these materials is herein summarized. The Redox Production Plant capacity has been reasonably predicted at about 112 tons uranium per month; this rate assumes only that critical mass control is achieved by the limitation of the possible volume accumulation at any point, and that the product concentrat… more
Date: June 28, 1951
Creator: Frame, J. M. & Tomlinson, R. E.
Partner: UNT Libraries Government Documents Department
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Temperature distribution in the concrete shield

Description: Report describing the temperature in the Brookhaven concrete shield proposed for the X reactor. The report details the methods and equations used to find the values that determined that the effect of the gun barrel assembly in cooling the concrete is negligible.
Date: April 28, 1952
Creator: Triplett, John R.
Partner: UNT Libraries Government Documents Department
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Design Considerations for a Lattice Test Pile

Description: From abstract: "The present paper proposes a lattice test pile, (or LTP) as an alternate to the continuing program of building up and tearing down of exponential piles."
Date: July 28, 1952
Creator: Horning, W. A.
Partner: UNT Libraries Government Documents Department
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Expansion of Hanford Works facilities

Description: This report discusses the feasibility of designing and building two 100 Areas at the Coyote Rapids site on the Columbia River. It incorporates the individual studies prepared by the Power and Mechanical Division-HDC-2241, Reactor Division-HDC-2239, Project Engineering Division-HDC-2244, Principal Engineer and HDC-2242, and the Engineering and Construction Services Division-HDC-2243, each outlining the proposed course of action and requirements for that facet of the contemplated work in which th… more
Date: June 28, 1951
Creator: Parker, J. S.
Partner: UNT Libraries Government Documents Department
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Fuels Preparation Department monthly report, January 1958

Description: This report describes the operation of the fuels preparation department for the month of January, 1958. Manufacturing, employee relations, process development, plant improvements, and financial operations are described.
Date: February 28, 1958
Partner: UNT Libraries Government Documents Department
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Pile Technology Division technical activities report: Materials Testing Group, March--April, 1950

Description: Brief summaries are given for each of the following activities for this two month period: (1) high water pressure channel (ANL-140); (2) KAPL fuel element tests (SR-79, Beta Experiment); (3) underwater facility for opening slugs; (4) strength of masonite at elevated temperatures; and (5) controlled temperature of graphite.
Date: June 28, 1950
Creator: Lambert, J. B.
Partner: UNT Libraries Government Documents Department
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Design of production test IP-280-A-FP: Irradiation of alloyed dingot uranium fuel elements

Description: Objective of this test is to authorize irradiation of alloyed, low hydrogen dingot uranium fuel elements on a pilot scale, and to monitor their performance. Initially, 25 tons per month of alloyed, low hydrogen dingot material will be charged for two months. Measured charges will be loaded with the initial 25 tons to monitor the stability of this material. Following a two-month delay in the monitor charging, and if the dingot meets all specifications, routine charging of quantities up to 60 ton… more
Date: August 28, 1959
Creator: Hall, R. E. & Hodgson, W. H.
Partner: UNT Libraries Government Documents Department
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CGI-844: 100-K coolant back-up system scope requirements

Description: Several decisions regarding basic project philosophy must be made in order to proceed with scope design and the preparation of equipment procurement specifcations. The purpose of this document is to present as much pertinent data as possible to allow the project representatives to become familiar with the problems involved. A meeting of Representatives is planned for the near future after receipt of project authorization to discuss the scope of this project and its relationship to CG-775. Emerg… more
Date: July 28, 1959
Creator: Watson, D. F.
Partner: UNT Libraries Government Documents Department
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Net return course - operational severity index formuli

Description: This document presents a nomograph from which the relationship between reactor operating parameters, tube power, and outlet temperature can be correlated with rupture rate. The index indicates the severity of the reactor climate during irradiation and does not include the metal quality parameters defined in the rupture rate equation. The general form of the Operational Severity Index Equation is OSI=P{sup 3.3}/1000{times}t{sub 0}{sup 8.7}/100, where OSI, is the unitless Operational Severity Ind… more
Date: December 28, 1959
Partner: UNT Libraries Government Documents Department
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