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Aircraft Reactor Test Removal and Disassembly

Description: Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
Date: 1960?
Creator: Abbatiello, A. A. & McQuilkin, F. R.
Partner: UNT Libraries Government Documents Department
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Calculation of Suspension Peptization

Description: Report regarding the combination the theories of flocculation, particle repulsion, and particle attraction in order to "understand the flocculation characteristics of TH02 suspensions" (p. 2).
Date: 1960
Creator: Sweeton, F. H.
Partner: UNT Libraries Government Documents Department
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Environmental Analysis of NS "Savannah" Operation at Camden

Description: Report regarding the nuclear ship "Savannah" and the consequences of nuclear activity that it would release into the surrounding area at its proposed startup site, Camden, New Jersey. Scenarios include activity being released into the atmosphere and hydrosphere, damage to equipment, and effects on a population.
Date: 1960
Creator: Cottrell, William B.; Mann, L. A.; Parker, F. L. & Schmidt, G. D.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Progress Report: May-October 1959

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 10, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Project Fabrication, Irradiation and Evaluation of Superheat Fuel Element SH-1 and SH-2

Description: The fabrication, irradiation and evaluation of the first two superheat fuel assemblies is described in detail. Experimental data indicate that, in general, the nuclear superheat fuel elements have performed satisfactorily under the testing conditions used. Certain problem areas which will influence future fuel element designs have been defined.
Date: April 7, 1960
Creator: Lees, E. A.; Boyle, R. F. & Spalaris, C. N.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960

Description: From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."
Date: April 29, 1960
Creator: Briggs, R. B.
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Third Quarter, January-March 1960

Description: From introduction: "This is the third of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: July 1, 1960
Creator: Pennington, R. T.
Partner: UNT Libraries Government Documents Department
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Solid State Division Semiannual Progress Report For Period Ending February 28, 1955

Description: This semiannual progress report and future reports will be published as two documents to permit a wider distribution of the unclassified material. The report numbers are assigned in sequence so that the two reports will fall together when filed by report number.
Date: July 12, 1960
Creator: Billington, D. S. & Crawford, J. H., Jr.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: February-April 1960

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. It includes descriptions of progress and studies conducted during the report period, with tables, illustrations, and photographs.
Date: August 9, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Partner: UNT Libraries Government Documents Department
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Automatic Control of T7 Tanker Boiling Water Reactor Propulsion System: Preliminary Design and Economic Evaluation

Description: From introduction: "This report sets forth the results of a technical and economic analysis of automatic propulsion system control as a possible design improvement in the direct cycle boiling water reactor propulsion system in a T7 tanker."
Date: September 1, 1960
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Second Quarter, October-December 1959

Description: From introduction: "This is the second of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: September 1960
Creator: U.S. Atomic Energy Commission
Partner: UNT Libraries Government Documents Department
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Evaluation of Experiment Off-gas System for the EGCR-LITR Capsule Experiment

Description: A proposed modification to the experiment off-gas system for the EGCR-LITR Capsule Experiment is evaluated by comparing the atmospheric radiation doses to laboratory personnel that could result in the event of an experiment failure while utilizing the present off-gas system to those doses that would result if various modifications to the existing system were effected. The modifications considered include the addition of an iodine vapor adsorber and a krypton-xenon adsorber. The addition of an i… more
Date: September 2, 1960
Creator: Adams, R. E. & Browning, W. E.
Partner: UNT Libraries Government Documents Department
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Solution of the Monoenergetic Boltzmann Equation in an Infinite Homogeneous Nonmultiplying Medium with Linearly Anisotropic Scattering and Isotropic Plane Source

Description: The solution of the monoenergetic Boltzmann equation in an infinite homogeneous, nonmultiplying medium with linearly anisotropic scattering and an isotropic plane source is given and compared with the corresponding solution for isotropic scattering. The effective source strength for the asymptotic flux turns out to be the same as that for isotropic scattering to first order in Σa/Σ.
Date: September 6, 1960
Creator: Inonu, Erdal
Partner: UNT Libraries Government Documents Department
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Thermal Characteristics of Fluid Flow in Pipes

Description: An investigation is made to determine the adequacy of presently used analog circuits in solving dynamic fluid flow heat transfer equations. A mathematical analysis is made of dynamic heat transfer in pipes with zero losses, with losses proportional to pip temperature, and with heat inputs. The results of this analysis are compared with analog results by means of generalized temperature versus time graphs. The analog circuit is found to be adequate for most conditions, but sometimes requires mod… more
Date: September 13, 1960
Creator: Hinton, D. B.
Partner: UNT Libraries Government Documents Department
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Some Elementary Results Concerning Escape Probabilities of Particles of Fixed Range Generated in Spheres

Description: Some results have been obtained which may be of use in studying the escape of fission fragments from slurry particles which contain fissioning material. Assuming that the fission fragments are of fixed range H, that they are generated uniformly and isotopically in a sphere of diameter D, the escape probability , mean path length, and path length distribution function have been derived.
Date: September 14, 1960
Creator: Tobias, Melvin
Partner: UNT Libraries Government Documents Department
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Momentum and Heat Transfer to a Fluid Flowing Turbulently in a Pipe

Description: A mathematical model is presented for the prediction of heat transfer coefficients for fully developed turbulent flow of fluids in circular pipes by analogy to the transfer of momentum. There is also presented an empirical velocity distribution equation derived from existing experimental data for use in the analogy model. Heat transfer coefficients for fluids with Prandtl numbers ranging from 0.01 to 100 and Reynolds numbers ranging from 5x10^3 to 10^7 are presented in tabular and graphical for… more
Date: September 15, 1960
Creator: Hefner, R. J.
Partner: UNT Libraries Government Documents Department
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Instruction Manual, Mercury Relay Pulse Generator Model 1-1212C

Description: The Model Q-1212C Pulser is a single frequency (60 pps) generator whose output waveform is characterized by a rise-time of less than 4 mµsec and, depending upon the method of termination, an exponential decay having a time constant of 300 or 600µsec. The waveform approximates that produced by a radiation detector. The waveform approximates that produced by a radiation detector. The maximum available output from the instrument is 10 volts, positive or negative polarity, and is continuously adjus… more
Date: September 20, 1960
Creator: Fairstein, E.
Partner: UNT Libraries Government Documents Department
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Precipitation of Crystalline Uranium and Thorium Peroxide: Applications to Fuel-Element Oxides and Purifications

Description: Departures from the usual precipitation method produced crystalline uranium peroxide in several forms. Three types of segregated needles were used in the preparation of three pellets for pellet-type elements. Densities of the pellets ranged from 93 to 97% of theoretical, depending on conditions of precipitation.
Date: September 21, 1960
Creator: Whetsel, H. B. & Dean, O. C.
Partner: UNT Libraries Government Documents Department
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Preliminary Analog Computer Study of the Small EGCR In-Pile Loops

Description: The ORNL analog computer was used to simulate four widely different experiment conditions in the small EGCR in-pile loops. Various control and safety systems were evaluated in each case. Curves are included which show the response to postulated accidents and component failures. The results indicate that one standard control and safety system will probably be adequate for a wide variety of test conditions.
Date: September 21, 1960
Creator: Ball, S. J. & Beasley, E. G.
Partner: UNT Libraries Government Documents Department
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