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Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office

Description: Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office

Description: Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Reactions yielding volatile oxides at high temperatures free energies of gaseous Al$sub 2$O, ZrO, ThO, TaO, ZrO$sub 2$, ThO$sub 2$, TaO$sub 2$, UO$sub 2$, and WO$sub 3$

Description: Although the oxides such as Al/sub 2/O/sub 3/, MgO, UO/sub 2/, ThO/sub 2/ , Be O, and ZrO/sub 2/ are used as refractory materials, very little reliable thermodynamic data predicting the stabilities of the gases in equilibrium with the solids at temperatures above 1700 deg C exist. In most cases the vapor pressures are not accurately known and in some cases the gaseous molecules are uncertain. Hence one experiences difficulties in attempting to predict ihe interaction of these oxides with the re… more
Date: January 1, 1958
Creator: Ackermann, R. J. & Thorn, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Estimate of the Probability and Consequences of Ignition of the HRT Charcoal Beds

Description: BS>The igition temperature of Columbia G activated charcoal in a flowing oxygen stream was determined to be 290 deg C under conditions simulating the inlet of the HRT charcoal beds. Calculations of charcoal temperatures resulting from beta decay of adsorbed fission gases from the HRT indicate that this temperature will not be reached provided the reacter power does not exceed 10 Mw with an accompanying oxygen flow not exceeding 2 liters/min. At lower power levels higher oxygen flow may be toler… more
Date: June 1, 1958
Creator: Adams, R. E. & Browning, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FISSION GAS HOLDUP TESTS ON HRT CHARCOAL BEDS

Description: Fission gas holdup tests on the HRT charcoal beds under simulated operating conditions are complete. A radioactive tracer technique developed for use in laboratory absorption studies was utilized. The efficiency of the charcoal beds, in regard to holdup of fission gases, exceeds design specifications. On the basis of these tests, the charcoal beds should perform satisfactorily with the l#T operating at 10 Mw with a total oxygen flow of 3 liters/min. or at 5 Mw with a total oxygen flow of 3.5 li… more
Date: April 1, 1958
Creator: Adams, R. E. & Browning, W. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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On the Calculation of Properties of Gases at High Temperatures. Technical Report No. 2

Description: The role of the potential of intermolecular force in determining properties of gases at elevated temperatures is discussed. Coefficients of viscosity and selfdiffusion, isotopic reduced themaal diffusion ratios, and second virial cofficients for helium, argon, and nitrogen at 1,000, 5,000, and 15,000 d K were calculated from extrapolated potentials and from beam potentials. (W.D.M.)
Date: August 1, 1958
Creator: Amdur, I. & Ross, J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PRELIMINARY REPORT OF FUSED SALT MIXTURE NO. 130 HEAT TRANSFER COEFFICIENT TEST

Description: Heat transfer data are presented over a Reyuolds Number range of 400 to 8000 for the test fused salt Mixture No. 130 (62 mol % LiF-37 mol % BeFi-1 mol % UF/sub 4/ for a calibrating used salt Mixture No. 30 (50 mol % NaF--46 mol % ZrF/ sub 4/--4 mol % UF/sub 4/) flowing inside round heat exchanger tubes. A prelima- nary equation is developed for predicting shell-side heat transfer coefficients for liquid metal in turbulent, longitudinal flow over a square tube array having a pitch/diameter ratio… more
Date: April 1, 1958
Creator: Amos, J.C.; MacPherson, R.E. & Senn, R.L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Uncollided Flux From Finite Circular and Rectangular Cylinders

Description: Expressions are derived for the uncollided flux from finite cylindrical sources with circular and rectangular cross sections. The source density is assumed to be completely arbitrary in the rectangular case and arbitrary to within independence of the aximuth in the circular case. The circular cylinder is assumed surrounded by an arbitrary number of concentric cylindrical shields and by plane circular shields above (or below) its upper (or lower) face. The rectangular source is treated with plan… more
Date: December 1, 1958
Creator: Anderson, D. C. & O'Reilly, B. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A MODIFIED PILE OSCILLATOR FOR NEUTRON CROSS-SECTION MEASUREMENTS

Description: A pile oscillator was designed, constructed, and operated at the Battelle Research Reactor. This pile oscillator cycles a specimen and a standard in the same container through an annular ion chamber located in the thermal column. This almost simultaneous oscillation of the standard and specimen eliminates errors caused by power drifts or fluctuations. The use of a continuous graphite rod for the container or carrier reduces undesirable scattering effects of the carrier. The oscillator was calib… more
Date: May 1, 1958
Creator: Anno, J.N.; Jung, R.G. & Chastain, J.W. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Progress report - bonding of DATB - progress report

Description: DATB (diaminotrinitrobenzine) pressings were made in an effort to find the most suitable binder. After successfully pressing ball milled DATB at 110 C,it was found that normal DATB (fine powder) could also be hot pressed at this temperature and 20,000 psi. Bulk density might vary from batch to batch.
Date: August 1, 1958
Creator: Archibald, P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Evaluation of the Radiation Protection Afforded by Residential Structures Against Distributed Sources

Description: A study was made to obtain information that could be used to evaluate the protection afforded by residences against radiation due to fallout. The sources used were Co/sup 60/ and Cs/sup 137/ and the radiation dosimeters used were pocket type ionization chambers. Measurements were made for distributed sources (400 Co/sup 60/ and 20 Cs/sup 137/) and for single sources located inside the structures (one each, 2-curie Co/sup 60/ and Cs/sup 137/). Attenuation measurements were made for five houses o… more
Date: September 1, 1958
Creator: Auxier, J. A.; Buchanan, J. O.; Eisenhauer, C. & Menker, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRT Pressure Vessel Temperatures During Operation - An Evaluation Using Data From Run 16

Description: A study was made of the data taken during HRT Run 16, concerning the temperatures and thermal stresses in the pressure vessel. By making heat balances across the blast shield cooling coils, the pressure vessel cooling system was shown to be performing satisfactorily. Estimates of the thermal stress in the pressure vessel wall show values which range from 1800 psi it low power to 6800 psi at 5 Mw. The thermal stress does not appear to be excessive in this power range. The over-all heat generatio… more
Date: July 1, 1958
Creator: Aven, R. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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IRRADIATION EFFECTS ON ZIRCONIUM-CLAD URANIUM-ZIRCONIUM FUEL PLATES

Description: This report summarizes the series of irradiations conducted in a Hanford reactor on specimens of zirconiumclad, uranium-- zirconium fuel plates containing 3, 6, and 14 vt.% highly (93.4%) enriched uranium. More than thirty fuel plates were exposed during the test program, which extended over a period of several years. (auth)
Date: February 1, 1958
Creator: Bailey, R.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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FREQUENCY RESPONSE ANALYSIS OF THE HRT FEEDWATER CONTROL SYSTEM

Description: A frequency response analysis is made of the HRT fuel feedwater system. The characteristics of the components are determined and used in the differential equation of the system. Using frequency response techniques, theoretical calculations of static and dynamic response characteristics are made for reactor operation at 5 Mw. The conclusions arrived at as a result of this analysis include suggestions for improving the present operation. (auth)
Date: April 1, 1958
Creator: Ball, S.J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Application of a First-Production Evaluation System to Help Assure Material Compatibility and Functional Reliance

Description: The ultimate achievement of a research and development program at Sandia. Corporation, as at any other AFX or DOD project, is the physical design of a component or weapon system of high reliability. The design accomplishment is initially established when the basic drawings and specifications are released for production. These drawings and specifications are often based on engineering evaluations of bread- .board and early so-called & quot;gold plated prototypes. However, the design accomplishme… more
Date: February 1, 1958
Creator: Ballard, Douglas
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Recycle in the Calder Hall Type Reactor

Description: The economiics and physics of four schemes of pIutonium recycle in the Calder Hall type reactor are considered. The four possible schemes are: (I) to blend the Pu produced In a run with fresh naturaI U for a subsequeut run; (2) to alloy the Pu with somie diIuent metal and fabricate the alloy Into high heat- transfer elements morc like MIR or PWR-sced type elements and"spike' a subsequent load of fresh natural U elemients with these Pu elemicnts; (3) to recycle half the spent U as well as the Pu… more
Date: January 1, 1958
Creator: Barbieri, L. J.; Webster, J. W. & Chow, K. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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ROLL CLADDING URANIUM-ZIRCONIUM AND URANIUM-ZIRCONIUM-NIOBIUM ALLOYS WITH ZIRCALOY-2 FOR PLATE-TYPE FUEL ELEMENTS

Description: Clad plate-type fuel elements containing U--5 wt.% Zr--1.5 wt.% Nb alloy cores integrally clad on all surfaces with Zircaloy-2 were developed for the Experimental Boiling Water Reactor (EBWR). These plates were prepared by roll bonding assembled components inside steel jackets at 850 deg C with 50% reduction in thickness to effect sound diffusion bonds at all component sufraces. To obtain reproducible sound bonds, uranium alloy core and cladding components were clean and free from surface conta… more
Date: February 1, 1958
Creator: Bean, C.H.; Macherey, R.E. & Lindgren, J.R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Dynamic Analysis of Natural Circulation Boiling Water Power Reactors

Description: Linear Feedback Control Theory is used to analyze the small-signal dynamic behavior of direct cycle, natural circulation boiling water reactor systems. Transfer functions for thermodynamic and hydraulic effects are derived in terms of reactor core and vessel dimensions. They are used to construct a theoretical system block diagram for the EBWR. (auth)
Date: March 1, 1958
Creator: Beckjord, E.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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PARTICLE ACCELERATORS. PART I. BIBLIOGRAPHY. PART II. LIST OF ACCELERATOR INSTALLATIONS

Description: References to accelerators and accelerator technology in the technical literature from July 1954 through June 1957 are listed in Section 1, the bibliography. Most of the references are taken from Nuclear Science Abstracts, Chemical Abstracts, Physics Abstracts, and Electrical Engineering Abstracts. In Section H, accelerator installations throughout the world are listed together with the types of particles accelerated and the energy and other characteristics of the machines. (auth)
Date: January 1, 1958
Creator: Behman, G.A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydraulic Cyclones for Thorium Oxide Particle Size Classification

Description: Results are reported concerning studies of hydraulic cyclones (hydroclones) for application to particle size classification of ThO/sub 2/. Tests were run with a 0.50-in. diam. hydroclone. It was shown that a single pass through this hydroclone would reduce the material greater than 10 mu from 12 wt.% to less than 1% while the mean diameter was reduced from 1.7 to 0.9 mu . When the overflow (fine) fraction was again pumped through the hydroclone, the overflow solids from the second pass were 98 … more
Date: February 1, 1958
Creator: Bennett, L. L. & Thomas, D. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Studies of the Corrosion of Aisi 304 Stainless Steel and Aisi 4135 Carbon Steel Exposed to Saturated Solutions of Boric Acid

Description: AISI 304 stainless steel and AISI 4135 carbon steel specimens were exposed to five wt.% (70 F) and thirteen wt.% (140 F) boric acid solutions. These are essentially saturation concentrations. After four weeks exposure it was found that the AISI 304 stainless steel was not attacked under these conditions but that the carbon steel had developed considerable corrosion products in the form of scale. It was found that the attack on carbon steel at 70 F in a five wt.% boric acid solution was greatly … more
Date: November 1, 1958
Creator: Bergen, C. R. & Whyte, D. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Effects of Alpha Particles on Uranium Hexafluoride

Description: Alpha irradiation of uranium hexafluoride results in the formation of fluorine and intermediate, solid uranium fluorides: these products react with each other, apparently by a radiation-induced process. to reform uranium hexifluoride. The number of molecules of uranium hexafluoride decomposed, excluding recombiapproximately 1 in the temperature range 21 to 87 deg C. Irradiation of a mixture of fluorine and uranium hexafluoride in a vessel containing uranium fluorides substantistes the postulate… more
Date: June 1, 1958
Creator: Bernhardt, H. A.; Davis, W. Jr. & Shiflett, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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