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The Scattering of Thermal Radiation Into Open Underground Shelters

Description: From Introduction: "The elimination of the burn hazard in shelters depends upon a separate, systematic investigation of each suspected agent. The purpose of the present investigation was to evaluate the contribution made by radiant energy and, if such contribution proved to be significant, to suggest means of eliminating this component."
Date: May 1959
Creator: Davis, T. P.; Miller, N. D.; Ely, T. S.; Basso, J. A. & Pearse, H. E.
Partner: UNT Libraries Government Documents Department
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Strontium Program: Quarterly Summary Report, May 29, 1959

Description: From Abstract: "This report is one of a sequence of quarterly reports, each designed to up-date its predecessor beginning with HASL-42, "Environmental Contamination from Weapon Tests". Herein are presented data which have accrued since HASL-55. Levels of strontinum-90 in fallout, milk, air, water, vegetation, foods, and bone are given, based on data available from February 1, 1959 to May 20, 1959."
Date: May 29, 1959
Creator: Hardy, Edward P., Jr. & Klein, Stanley
Partner: UNT Libraries Government Documents Department
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Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Description: Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design criteria, and the fabrication of reactor components" (p. 1).
Date: May 25, 1959
Creator: Aerojet-General Corporation
Partner: UNT Libraries Government Documents Department
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An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

Description: From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
Date: May 1, 1959
Creator: Rieck, H. G.; Ratcliffe, C. A. & Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department
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Description of Purex Plant Process

Description: Description of Purex plant process for irradiated uranium for the separation and decontamination of plutonium and uranium from each other and from fission products.
Date: May 19, 1959
Creator: Irish, E. R.
Partner: UNT Libraries Government Documents Department
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Scram transient tests PT-IP-249-C

Description: The purpose of this production test is to provide a standard method of obtaining scram transient reactivity information at the eight reactors, under conditions conducive to valid data. These conditions include the bypassing of the Panellit system at a low power level for a short, controlled period of time during May 1959.
Date: May 25, 1959
Creator: Bowers, C.E.
Partner: UNT Libraries Government Documents Department
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Elimination of TOA corrosion limits

Description: In 1958, planned large scale use of the new I & E slug geometry at more severe operating conditions than had been generally experienced suggested a possible compromise in reactor life and safety if a reasonable degree of rupture control with the new type of element was not maintained. The formalized slug corrosion limit (Top-of-Annulus limit) was issued as a Process Standard at the time of the full-scale loading of I & E geometry fuel elements to provide this limit for reactor operation. The loading of I & E slugs at all reactors has been accomplished and initial power level increases have been made. To date, 67 I & E ruptures have been sustained including both `hole` and `annulus` failures. The type and behavior of ruptures to be expected with I & E geometry are now characterized. Recent studies have indicated that the I & E failure experience is consistent with the general mathematical rupture model formulated from analysis of solid slug experience. Increased confidence in the use of this model in combination with Optimization Studies permits greater emphasis to be placed on the rupture model as a guide for reactor operation. It is the purpose of this report to present the basis for substituting the rupture model for the TOA corrosion limits for rupture control purposes.
Date: May 12, 1959
Creator: Graves, S.M.
Partner: UNT Libraries Government Documents Department
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Review of Soils Design, Construction, and Performance Observations: Lookout Point Dam, Oregon

Description: This report reviews the performance of the Lookout Point Dam located on the Middle Fork of the Willamette River in Oregon. "This study is one of a series of similar studies of the foundation and soil mechanics features of earth dams [...] In these studies original design data are reviewed, construction experience is summarized, and performance fo the completed structures is compared with design predictions to provide information for use in the design and construction of future similar projects" (p. 1).
Date: May 1959
Creator: Waterways Experiment Station (U.S.)
Partner: UNT Libraries Government Documents Department
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Handbook: A Technique for Preparing Desert Terrain Analogs

Description: "A technique is described whereby desert areas selected for terrain comparison are mapped in terms of general terrain factors, geometry factors, ground factors, and vegetation" (p. vii).
Date: May 1959
Creator: Van Lopik, Jack R. & Kolb, Charles R.
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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Experimental Gas-Cooled Reactor: Preliminary Hazards Summary Report

Description: From introduction: This report describes progress during the first quarter on all phases of the ANPP Code Development Program, Pressurized Water Task. The objective of this program is the development of a nuclear physical model and its calculation code for pressurized-water-cooled and moderated reactors to predict accurately reactivity, rod positions, and power distributions at operating temperatures, and reactor life from a nuclear standpoint.
Date: May 1959
Partner: UNT Libraries Government Documents Department
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Remote Radiological Monitoring

Description: From abstract: A gamma-radiation telemetering system was utilized by Civil Effects Test Group personnel to measure fallout levels at the Nevada Test Site from the vicinity of Ground Zero out to, and including, an area bounded by Reno, Nevada; Salt Lake City, Utah; Kingman, Arizona; and Barstow, California.
Date: May 1, 1959
Creator: Sigoloff, Sanford C. & Borella, H. M.
Partner: UNT Libraries Government Documents Department
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Report of the Sodium Heavy-Water Reactor Task Force: May 1959

Description: "The sodium-heavy-water reactor concept was evaluated on the basis of (1) its technical feasibility and (2) its potential for the economical production of electric power."
Date: May 1959
Partner: UNT Libraries Government Documents Department
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High-Frequency Titration as Applied to the Determination of Thorium, Uranium, Sulfate, and Free Acid. Parts 1-51

Description: The technique of high-frequency titrimetry was applied to the determination of thorium, uranium, sulfate, and free acid. In Part I, the reproducibility of the method for the titration of standard solutions that contained 50 rag of thorium in the absence of interferences is established. Under these conditions, the coefficient of variation of the method was <1%. In Part II, the effect of uranium on the highfrequency titration of thorium, as well as the application of the method to actual samples, is discussed. Uranium in a ratio of 5 to 1 to thorium can be tolerated. When the method is applied to the analysis of representative samples, the coefficient of variation is 1%. Attempts to determine uranium by high-frequency titration with 8-quinolinol were unsuccessful. Tests on this titration and possible reasons for its failure are discussed in Part III. The application of the high-frequency titration method to the determination of sulfate in solutions of uranyl sulfate is described in Part IV. The coefficient of variation, on titrating 40 to 70 mg of sulfate with barium chloride after the uranium is masked with citrate or fluoride, is 2%. In Part V, the high-frequency titration of free acid in solutions of uranyl sulfate is dis cussed. Uranium up to 350 mg, which was the highest level tested, does not interfere. The coefficient of variation of the method is -2%. (auth)
Date: May 11, 1959
Creator: Menis, O
Partner: UNT Libraries Government Documents Department
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Reprocessing of Are Fuel, Volatility Pilot Plant Runs E-1 and E-2

Description: After two batches ( approximately 340 kg) of fluoride salt from the ARE were reprocessed, a pilot plant operations were terminated because of a leak through which an estimated 780 g of uranium (as UF/sub 6/ escaped. Of the 21 kg of highly enriched uranium in the feed, 93.12% was collected as UF/sub 6/ product, 0.13% represented measured losses, and 3.72% was unaccounted for (leak). An additional 3.03% was reclaimed from NaF beds and equipment washes. The produce met both chemical purity and activity specifications for product level UF/ sub 6/. Decontamination from fission products was essentially complete. A gross gamma decontamination factor was apparently limited by the low activity of the feed salt. (auth)
Date: May 11, 1959
Creator: Whitmarsh, C. L.
Partner: UNT Libraries Government Documents Department
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Volatility: Fluorinator Design FV-100, Zr-U Fuel Element Processing Phase

Description: Volatility Pilot Plant Mark III Fluorinator is a doublechamber type vessel, each chamber 2 1/2 ft by 16 in. outside diameter separated by a 5-in. pipe 15 in. long. ASME flanged and dished heads are used for the chamber tops and conical sections with a 60 deg apex angle for the chamber bottoms. A new furnace designed to maintain the complete lower chamber (molten salt+ freeboard) above melt temperature is to eliminate past experiences of salt solidification on the wall, heads, and in or on the internal process lines. External pipe runs are autoresistance heated to allow melting and drain back of salt plugs. The upper chamber serves as a gas de-entrainment and solids precipitation device to retain most of the entrained salt and condensable fluorides in the 100 to 400 deg C range. (auth)
Date: May 28, 1959
Creator: Ruch, J. B.
Partner: UNT Libraries Government Documents Department
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Determination of Thickness of Oxide Film on Phosphor Bronze

Description: The thickness of an oxide film on phosphor bronze helices was determined by first establishing the oxygen content of the helix "as received" and after cleansing with nitric acid. Based on the assumption that the difference between the two values was the oxygen in the film, and that the film consisted entirely of cupric oxide, the thickness of the film was calculated from the density of cupric oxide, weight of film, and surface area of film. A value of 1080 A was calculated as the thickness by this method. (auth)
Date: May 19, 1959
Creator: White, J. C.
Partner: UNT Libraries Government Documents Department
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Large Exploding Wires-Correlation to Small Wires and Pause Time Versus Length Dependency

Description: The results of small exploding-wire studies were found to be capable of direct extrapolation to larger wires (an increase in cross-sectional area of 1500 to 1500 from the small wires). Copper wires up to 40 mils in diameter and iron wires to 62 mils in diameter were studied for use as fuses. in lengths up to 18 in. A dependency between pause time (the time between system current cut-off and current restrike) and wire length is described for several sizes of copper wires exploded with 16.5- and 49.5-kilojoule sources. The role of wire confinement is discussed in connection with establishment of the pause. (auth)
Date: May 1, 1959
Creator: Cnare, E. C. & Neilson, F. W.
Partner: UNT Libraries Government Documents Department
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PROBLEMS IN ACCOUNTABILITY MEASUREMENTS ASSOCIATED WITH THE INTERIM CHEMICAL PROCESSING PROGRAM

Description: Available knowledge of precision limits in S.S. accountability measurements and/or calculations by reactor and chemical processing groups is surveyed and summarized. Experienee in comparisons of reactor (production and research) calculations vs. chemical plant accountability measurements is also reported. A general tentative conclusion is that available precisions ( plus or minus 0.54 to plus or minus 0.78%) in chemical plant measurements (bulk and analytical) for fissionable material accountability is superior to the variable precision ( plus or minus 1.0 to 1l.0%) possible by calculations (nuclear and/or engineering) of power reactor systems; however, with operation and empirical experience (e.g., after two or three core loadings), it is believed that calculations for given reactors can attain acceptable precisions, e,g., less than plus or minus 1.0%. It may be proposed that fuel payments be made as follows: 90% of fuel value based on reactor calculations, an additional 5% based on dissolver analyses, and final settlement based on chemical plant material balance (product plus loss analyses). (auth)
Date: May 28, 1959
Creator: Arnold, E D & Gresky, A T
Partner: UNT Libraries Government Documents Department
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Design Criteria for a Pile Oscillator

Description: An elementary discussion is given of the reactor parameters which determine the signal-to-noise ratio obtainable with a pile oscillator. (auth)
Date: May 25, 1959
Creator: Dresner, L.
Partner: UNT Libraries Government Documents Department
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