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Time behavior of a critical reactor pulsed with a large square wave source

Description: In a previous Naval Application memorandum, a discussion was given of what happens to the power level of a reactor when an instantaneous, very large neutron source is introduced. The motivation for the problem arises from the question of what happens when a nuclear bomb is detonated near a reactor powered missile. This present memorandum looks at the same problem as that which is discussed in the previous memorandum but in slightly more detail. The results obtained are essentially the same as t… more
Date: October 2, 1962
Creator: Barnett, C.
Partner: UNT Libraries Government Documents Department
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A Rapid Beam Deflector for the Brookhaven AGS

Description: An air cored pulse deflection coil has been constructed for the Brookhaven AGS. The system produces a deflecting pulse with a peak radial deflection of 2.5 cms and duration of 70 microseconds. Beam spill duration of 15 to 50 microseconds from the target is readily achieved. One deflector has given satisfactory service for over a year and a second unit has been installed this summer.
Date: October 2, 1962
Creator: Brown, H. N.; Culwick, B. B. & Forsyth, E. B.
Partner: UNT Libraries Government Documents Department
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Production Test IP-490-A-FP: Evaluation of diffusion bonded fuel elements

Description: The objectives of this test are to determine the gross dimensional stability of hot pressed fuel and to evaluate bond quality differences between Al-Si bonds and solid state diffusion bonds. Irradiation testing will be conducted at C Reactor and will be carried out in two parts: Part 1, Sylcor and Hanford hot press diffusion bonding processes will be compared to the Hanford Al-Si bonding process. Eighteen (18) measured monitor columns of CVNS fuel elements will be irradiated to an 800 MWD/T goa… more
Date: May 2, 1962
Creator: Clinton, M. A.
Partner: UNT Libraries Government Documents Department
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Simple High-Voltage Trapezoidal Pulse Generator

Description: From abstract: "A description is given of a simple circuit used to produce negative voltage pulses up to 60 kilovolts with a portion rising with constant slope up to 10 kilovolts per microsecond."
Date: April 2, 1962
Creator: Gonella, Luigi
Partner: UNT Libraries Government Documents Department
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A method to determine optimum venturi size

Description: The Hanford reactors have undergone numerous hydraulic changes which have increased production output either directly, as in the cases of raising bulk limited power levels, or indirectly, such as reorificing to accommodate major advances in pile flattening efficiencies. Unfortunately, whenever major hydraulic changes occur, Panellit pressures that had been prevalent also change, sometimes to the extent that efficient pile operation is affected. Therefore, when hydraulic changes occur, an invest… more
Date: April 2, 1962
Creator: Radtke, W. H.
Partner: UNT Libraries Government Documents Department
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The Half-Life and Gamma Ray Abundance of Cs-137

Description: The nuclide Cs-137 is a fission product commonly used for measurement of uranium burnup in irradiated uranium fuel by the fission product to uranium ratio method. In the application of this method, the largest single error introduced in the measurement of burnup is the uncertainty in the half-life of Cs-137. Because of the uncertainty in this value and its importance in nuclear fuel burnup analysis, a reinvestigation was undertaken to obtain a more accurate value using the mass spectrometric me… more
Date: June 2, 1962
Creator: Rider, B. F.; Peterson, J. P. & Ruiz, C. P.
Partner: UNT Libraries Government Documents Department
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Cover sheet for a Hanford Historial Document for public availability

Description: The following criteria defines the objectives, bases and functional requirements that shall govern the preparation of the final design for the zirconium process tube installation program at the 100-K Areas. As a result of this program, reduced operating costs and increased production can be achieved. The present central zone aluminum tubes in the 100-K Reactors require replacement every to to three years to prevent excessive failures resulting from the thinning of the tube walls by corrosion. R… more
Date: August 2, 1962
Creator: Schack, M. H.
Partner: UNT Libraries Government Documents Department
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Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity

Description: From Abstract: "The diffusion cooling coefficient in graphite has been determined by measuring the change in the asymptotic average velocity with buckling, by pulsed neutron methods. The times necessary to establish equilibrium spectra in graphite and heavy water have been measured and are reported."
Date: January 2, 1962
Creator: Starr, E. & De Villiers, J. W. L. (Jacobus Wynand Louw)
Partner: UNT Libraries Government Documents Department
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The Application of an Operational Reactivity Accounting System Based on One-Group Diffusion Theory

Description: HW-70780, {open_quotes}An Operational Reactivity Accounting System Based on One-Group Diffusion Theory{close_quotes} describes a reactivity accounting system which is an improvement over the present {open_quotes}flux-squared weighting{close_quotes} system. Several changes and additions have been made which will simplify and increase the accuracy of the system described in the parent document. The changes occur primarily in the application of the system and are compatible with diffusion theory a… more
Date: July 2, 1962
Creator: Stewart, S. L.
Partner: UNT Libraries Government Documents Department
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The Hydrolysis of the Rare-Earth Carbides

Description: From introductory paragraph: "This report concerns the hydrolysis of rare-earth dicarbides, sesquicarbides, solid solutions of carbon in rare-earth metals as well as rare-earth carbon alloys of varying compositions. Many of the carbide samples used in this study were those which had been studied by Gschneider (9)(7) and had been preserved in evacuated, sealed tubes. Some additional preparations of the sesquicarbides were made especially for these studies. The hydrolytic reactions were carried o… more
Date: July 2, 1962
Creator: Svec, Harry J. (Harry John), 1918-; Capellen, Jennings & Saalfeld, Fred E.
Partner: UNT Libraries Government Documents Department
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High Performance UO2 Program Third Quarterly Progress Report: October-December 1961

Description: The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding of the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely, fission gas release and central melting in fuel rods.
Date: January 2, 1962
Creator: Weidenbaum, B.
Partner: UNT Libraries Government Documents Department
open access

A Computer Program for Calculating One-Dimensional Hydrodynamic Flow: KO Code

Description: A computer program is described for the solution of shock, detonation, and spall problems for one-dimensional linear, cylindrical, or spherical hydrodynamic flow. The Flume option is used for calculating flow- through arbitrary cross sections. (R.J.S.)
Date: July 2, 1962
Creator: Wilkins, M.; French, J. & Giroux, R.
Partner: UNT Libraries Government Documents Department
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