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Cross Section Program at ORNL

Description: ORNL's Cross Section Program focuses on measuring, evaluating, and applying nuclear data for nuclear criticality safety, reactor analysis, and astrophysics. This technical report discuses (1) Capture Cross Sections; (2) Activation Cross Sections at 195 Kev, (3) Al27(n,alpha)Na24 Cross Section, (4) S-Wave Detector of Deuteron Polarization and 14-Mev Polarized Neutron Source, (5) Coulomb Excitation of the First and Second 2+ States in Some Medium-weight Even-even Nuclei, (6) A Reaction Product Ma… more
Date: February 25, 1959
Creator: Harvey, J. A. (John A.) & Fowler, J. L.
Partner: UNT Libraries Government Documents Department
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Analysis of Neutron Pulses in a Godiva-Type Reactor

Description: Some calculations have been made to estimate the characteristics of a neutron-burst type fast reactor similar to Godiva but made up of relatively small component parts--the so-called "layered assembly." One spherical and three cylindrical assemblies have been considered. Critical masses, assuming 5% voids, range from 58 to 65 kg of 93.4% enriched U/sup 235/. For a reactivity addition of 0.33 dollars above prompt critical bursts between 2 x 10/sup 17/ and 6.7 x 10/ sup 17/ fissions were computed… more
Date: February 25, 1959
Creator: Nestor, C. W. & Tobias, Melvin
Partner: UNT Libraries Government Documents Department
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Effects of Fuel Burn-Up on the Dissolution Process-I

Description: Data on the effects of nuclear fuel burnup on dissolution rates and U losses of a few fuel types are summarized. Burnup to the 40% level produced very little effect on the rate of solution of stainless steel-UO/sub 2/ fuel elements in solutions of the Darex type. Beyond passivation, burnup to the 250 Mwd/T level did not produce a large effect on the rate of decladding nor on the U losses in the Sulfex process. Burnup to the 15% or 4300 Mwd/T level produced little or no effect on the rate of dec… more
Date: March 25, 1959
Creator: Davis, W., Jr.
Partner: UNT Libraries Government Documents Department
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Comparison of Two Colorimetric Methods for Uranium

Description: In order to establish the feasibility of using two colorimetric methods for the determination of uranium interchangeably, according to the interferences encountered in a particular sample. Results were obtained by each of the methods and compared. The dibenzoyl methane method and the ethyl acetate-ammonium thiocyanate procedure were compared on the basis of values secured on the same day, on different days, on an analysis of the variance, and on an analysis of the residual error for the methods… more
Date: March 25, 1959
Creator: McCutchen, Roberta L.
Partner: UNT Libraries Government Documents Department
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Spectrophotometry of Molten Fluoride Salts: Status Report

Description: Progress made in the field of spectrophotometry of molten fluoride salts is summarized. The high-temperature cell assembly designed and fabricated for use in this work is described, as well as the various types of sample containers used. Spectra of nickel fluoride, cobalt fluoride, chromic fluoride, and uranium tetrafluoride in LiF--NaF-KF (46.5-11.5--42 mole%) are presented. (auth).
Date: March 25, 1959
Creator: White, J. C.
Partner: UNT Libraries Government Documents Department
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An Evaluation of Electro-Machining for the Analysis of Metal Surfaces

Description: A procedure is described for the uniform removal of very thin sections of metal surfaces by electrolysis. Equipment requirements and the various parameters affecting operation are considered, and the results of applying the technique to studies of solid-state diffusion are discussed. The technique appears to offer considerable promise for evaluating chemical changes at metal surfaces which have taken place as a result of corrosion or diffusion processes. (auth).
Date: June 25, 1959
Creator: DeVan, J. H.
Partner: UNT Libraries Government Documents Department
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Defect testing of coextruded uranium-zircaloy-II clad fuel material in a 300 C out-of-reactor recirculating water loop: Interim report

Description: A major problem in the development of a pressurized water reactor coolant system for the NPS is the rupture performance of the fuel elements. As water temperatures are increased to 300 C, uranium corrosion rates increase rapidly. Swelling of the uranium fuel by corrosion could cause the process tube to burst or reduce the tube cooling water flow below acceptable limits. The desirability of slow cooling of the water to avoid thermal shocks to the reactor piping after a rupture is detected furthe… more
Date: September 25, 1959
Creator: Hayden, K. D. & Goffard, J. W.
Partner: UNT Libraries Government Documents Department
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Gamma Rays from Inelastic Scattering of 14-Mev Neutrons on Pb²⁰⁸

Description: Abstract: "The cross section for the production of 2.61-Mev gamma rays from the Pb-208(n, n')Pb-208* reaction has been measured for five different angles from 50 to 130 degrees. The angular distribution appears to be isotropic within the precision of the experiments, and leads to an integrated cross section of 25.5 +/- 4.6 millibarns."
Date: August 25, 1959
Creator: Hallett, Edward & Jensen, Roger
Partner: UNT Libraries Government Documents Department
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9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709

Description: The following document describes the usage and purpose of the neutron diffusion theory reactor program 9-Zoom, a memory-contained program that takes advantage of 709 features such as, for example, preferential order of multiply by zero, and for small problems approaches input-output limitations with excellent convergence properties.
Date: August 25, 1959
Creator: Stone, S. P.; Collins, E. T. & Lenihan, S. R.
Partner: UNT Libraries Government Documents Department
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Specifications: Laboratory hot press process for {open_quotes}C{close_quotes}size I & E fuel elements

Description: Hot press canning of internally and externally cooled fuel elements has been developed to a point where the process is feasible. Complete specifications have been written for the process covering component, dies and punches, furnace construction, nickel plating, component cleaning, component assembly, sizing, hot pressing and inspection. Drawings covering each major item are included.
Date: September 25, 1959
Creator: Tverberg, J. C.
Partner: UNT Libraries Government Documents Department
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Liquid Metal Fuel Reactor Experiment Annual Technical Report: 1958

Description: Annual report of the Liquid Metal Fuel Reactor Experiment describing progress during calendar year 1958 and as well as an evaluation of progress and plans for future work.
Date: March 25, 1959
Creator: Babcock & Wilcox Company
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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Redox in-line monitoring instruments information manual

Description: The in-line monitoring instruments installed in the Redox plant in the late 1950s consisted of six gamma monitors, a single channel gamma spectrometer, an alpha monitor, and a neutron counter. A gamma monitor on the steam condensate outlet line and a uranium monitor on the 2DFS stream were to be added at a later date. The first section of this information manual describes the in-line gamma monitors and gives operating instructions for them. The second section covers the alpha monitor, and the t… more
Date: March 25, 1959
Creator: Erlandson, O. D.
Partner: UNT Libraries Government Documents Department
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Reactor Automatic Control and Load Swing Test. Test Results DL-S-144 (T-554924). Section I. Second Performance

Description: The purpose of this test was to determine the controlling ability of the Reactor Power and Temperature Control System and to determine the operational characteristics of the station during load swings after change of operating conditions from 523 F, 2000 psi, to 500 F, 1800 psi. The Reactor Power and Temperature Control System satisfactorily controlled rod movements to maintain all primary plant parameters within their individual limits during steady state operation and during ramp function loa… more
Date: March 25, 1959
Creator: Mafrica, Roces
Partner: UNT Libraries Government Documents Department
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The Compound CuO-3UO3

Description: A double oxide of uranium and copper has been found to exist at 300'C in the four-component system UO3-CuO-SO3-H2O. This new compound is shown to be CuO-3UO3. The method of preparation, analyses, and characterization of the compound are given. Some comments are made with regard to the homogeneous reactor fuel solution.
Date: August 25, 1959
Creator: Gill, J. S. & Marshall, W. L.
Partner: UNT Libraries Government Documents Department
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Spectrographic Analysis of Normal Human Tissue From Richmond, Virginia

Description: As a part of the Internal Dose Program, normal human tissues are analyzed spectrographically for approximately 40 minor and trace elements. This study is performed by the Health Physics Division and the Physics Department, University of Tennessee, under Subcontract 380. Because the amount of data is large, central files reports have been issued which include the data on all tissues received from a city. This is the sixth report in the series, and all tissues here reported upon were received fro… more
Date: August 25, 1959
Creator: Tipton, I. H.; Cook, M. J.; Foland, J. M.; Rittner, Johanna; Hardwick, Michael & McDaniel, K. K.
Partner: UNT Libraries Government Documents Department
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Reactor Plant Container Air Cooling System. Section III. Second Performance. Test Results DL-S-136 (T-550090)

Description: The purpose of this test was to determine the performance of the Reactor Plant Container Air Cooling System with four reactor coolant loops at operating temperature. Due to the fact that the test was performed with the chamber door open, no significant conclusion can be arrived at concerning the efficiency of the Air Cool System. The 1B supply fan circulated approximately 20 per cent less air than the 1A fan during the test. Later investigation revealed that the turning vanes above the 1B dampe… more
Date: March 25, 1959
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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Expansion program 190 Building studies results

Description: It is the objective of this study to investigate preliminary expansion program requirements for process water, as supplied by 190 Building equipment; from the point of view of practical pumping, flywheel and pump suction head requirements. These requirements are to be determined at this time in such a form and accuracy as to be useful in refined estimating for budget study purposes. In order to obtain the objectives of this study at this time it has been decided to consider five different condi… more
Date: November 25, 1959
Creator: Quackenbush, C. 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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Estimate of Potential Fuel Reprocessing Revision #28 - Part A

Description: The power and estimated reprocessing load are tabulated for existing and proposed United States and United States-built reactors of 10 Kw or greater thermal power.
Date: June 25, 1959
Creator: Ullmann, J. W.
Partner: UNT Libraries Government Documents Department
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Theory of Asymmetric Arrays of Control Rods in Nuclear Reactors

Description: Introduction: Seldom does the actual arrangement of control elements in a nuclear reactor confers to the ideal and convenient mathematical array. In order to achieve shim control. safety and regulation, it is desirable to design with rods of different sizes and materials. With given fuel element arrangement, typically in square or hexagonal lattice spacing, there will be rods located at different distances form the center of the core and from each other. As the reactor operates, absorbers wil… more
Date: April 25, 1959
Creator: Murray, Raymond L.
Partner: UNT Libraries Government Documents Department
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