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The Snap Ii Power Conversion System Topical Report No. 12. Boiler Development

Description: The SNAP II boilers which were designed are summarized. As shown by test results from the three boilers which were tested, a continuous progress in design was achieved. These designs were based on test data from both the SNAP I and SNAP II programs. As the quantity of data increased, physical models describing the heat transfer process were developed. These physical models provide the necessary correlation parameters which permit the extension of existing data to advanced design. Preliminary te… more
Date: July 17, 1961
Creator: Gido, R. G.; Koestel, A.; Haller, H. C.; Huber, D. D. & Deibel, D. L.
Partner: UNT Libraries Government Documents Department
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New Solutions of the Boltzmann Equation for Monoenergetic Neutron Transport in Spherical Geometry

Description: Solutions of the Boltzmann equation for monoenergetic neutron transport in spherical geometry are derived which are respectively singular and regular at the center of the sphere. A few specific partial singular solutions are presented. The regular solutions in spherical geometry are constructed by superposition of solutions in plane geometry which belong to the same k. Finally, the solutions are compared with their representations by a series of spherical harmonics. (D. L.C.)
Date: November 17, 1961
Creator: Kofink, W.
Partner: UNT Libraries Government Documents Department
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Analytical Chemistry of the Polyphosphates

Description: Additional data were obtained on the separation of linear polymers from cyclic polymers by precipitation with barium chloride. An unexpected peak was observed in the anion-exchange chromatography of a sodium poly-phosphate of n-bar average degree of polymerization) = 6, and the compound represented by this peak was isolated. An end-group titration of this compound by microtechnique proved unequivocally that it is a cyclic phosphate. Although the identification (number of phosphorus atoms per mo… more
Date: October 17, 1961
Creator: Rieman, W., III & Rothbart, H. L.
Partner: UNT Libraries Government Documents Department
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AN IBM 7090 FORTRAN PROGRAM FOR ASME UNFIRED PRESSURE VESSEL DESIGN AND PRELIMINARY COST ESTIMATION

Description: An IBM 7090 FORTRAN program was written for the preliminary design and cost estimation of unfired pressure vessels with or without a jacket. Both vessel and jacket designs conform to the 1959 ASME Boiler and Pressure Vessel Code, Section VIII, Unfired Pressure Vessels. Vessels and jackets from 5 in. pipe through 84 in. o.d. and 1/4 in. through 1 1/2 in. in metal thickness may be designed by this program as written. Total vessel cost is the sum of metal and fabrication costs, each on a weight ba… more
Date: October 17, 1962
Creator: Prince, C. E. & Milford, R. P.
Partner: UNT Libraries Government Documents Department
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Computer Technology and Congressional Operations: Selected References

Description: This report serves as a series of citations indicating an increased interest in automatic data processing (ADP) within the United States Congress.
Date: July 17, 1969
Creator: Chartrand, Robert L. & Ayton, Mauree W.
Partner: UNT Libraries Government Documents Department
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Local Welfare Administrators' Comments On the "Welfare Crisis."

Description: This report discusses local welfare and it points out a wide range of opinions and proposals reflected in the discussions of proposals for improving or changing the exiting system.
Date: December 17, 1968
Creator: Malone, Margaret
Partner: UNT Libraries Government Documents Department
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THE CYCLOTRON RESONANCE INSTABILITY WITH NEGATIVE MASS IONS

Description: Both the effect of resonant coupling of ion cyclotron motion to electron plasma oscillations, as previously discussed by Harris, and the effect of a negative radial gradient in a magnetic mirror field, the so-called "negative mass'' effect, were combined in an approximate calculation for the threshold for electrostatic instability in DCX. The two mechanisms for instability were found to act more or less independently. (auth)
Date: October 17, 1961
Creator: Fowler, T.K. & Harris, E.G.
Partner: UNT Libraries Government Documents Department
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OPTIMUM FILL VOLUMES IN POT CALCINATION OF RADIOACTIVE WASTES

Description: The 15,000 MW nuclear economy assumed for the long range study of pot calcination costs reported earlier was used as a basis for calculating optimum fill volumes. An algebraic expression was developed for cost as a functmon of the normalized radius of the central void space in a partially filled vessel. Minima of this expression were found for acmdmc and neutralized wastes in 6, 12, and 24in.-diameter vessels. Optimum fill volumes decreased as vessel diameter increased, varying for acidic waste… more
Date: November 17, 1961
Creator: Perona, J.J.
Partner: UNT Libraries Government Documents Department
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METALLURGY DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING MAY 31, 1961

Description: >Fundamental Alloying. Studies of crystal structures, reactions at metal surfaces, spectroscopy of molten salts, mechanical deformation, and alloy theory are reported. Long-Range Applied Metallurgy. A thermal comparator is described and the characteristic temperature of U0/sub 2/ determined. Sintering studies were carried out on ThO/sub 2/. The diffusion of fission products in fuel and of Al/sup 26/ and Mn/sup 54/ in Al and the reaction of Be with UC were studied. Transformation and oxidation d… more
Date: August 17, 1961
Partner: UNT Libraries Government Documents Department
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Experiment Facilities of the Oak Ridge Graphite Reactor

Description: Up-to-date descriptive material and dimensional sketches of the ORNL Graphite Reactor and its experimental facilities are presented. (P.C.H.)
Date: August 17, 1962
Creator: Sheppard, S. D.
Partner: UNT Libraries Government Documents Department
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NEUTRON PHYSICS DIVISION ANNUAL PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 1, 1961

Description: Fifty-seven papers and l7 abstracts of papers are presented in the report. Fifty two of the papers are abstracted separately; in addition, a single abstract is written to cover the section on Plasma Physics Theory, which contains 3 papers and 8 abstracts of papers. The two brief papers not abstracted separately are concerned with fast neutron detection, and homogeneous critical assemblies of 3%enriched UF/sub 4/-paraffin systems. (T.F.H.)
Date: November 17, 1961
Partner: UNT Libraries Government Documents Department
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Determination of Maximum Permissible Irradiation of Type 3 (SM-2) Fuel Plates

Description: Two methods were used for predicting the maximum permissible burnup in type 3 (SM-2) fuel plates: use of analytical models and use of existing irradiation data on UO/sub 2/ stainless steel dispersion fuel plates. Results with two analytical models indicated that burnups above 100% U/35 are permissible. Comparison of the expected burnup with available irradiation data indicates that successful performance of type 3 replacement cores in SM-1, SM-1A, and PM-2A can be expected. (auth)
Date: March 17, 1962
Creator: Wilder, A. S. & Lelleman, R. W.
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey of Reactor Plant Container and Components After Shutdown "F" Survey. Core I, Seed 1. Test Results (T-612076). Section 4

Description: An investigation was conducted to obtain measurements of radiation levels inside the hemispherical heads of the 1-B heat exchanger. The radiation levels were measured at the handholes on two occasions with an interval of 640 hrs between them. A very large increase was noted and could be explained only by the possibility that the measurement survey points were not identical. (J.R.D.)
Date: October 17, 1960
Partner: UNT Libraries Government Documents Department
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Study of EOCR Modifications for Testing Fast Reactor Fuels

Description: Report issued by the APDA over studies conducted on "methods for increasing the power generation in a fast reactor fuel element test sample" (p. 9). The methods investigated are presented and discussed. This report includes tables, and illustrations.
Date: February 17, 1964
Creator: Ball, G.; DeFelice, J.; Edwards, J. J.; Jens, W. H.; Kovac, L. R.; Poggi, R. et al.
Partner: UNT Libraries Government Documents Department
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Research Study on Neutron Interactions in Matter as Related to Image Formation

Description: From abstract: "In this report we present data obtained with the optical simulation apparatus on image quality as a function of the parameters of neutron scattering and image detector resolution...Also included in this report is a brief description of a large area (5 inch diameter) neutron beam exposure facility being set up at the reactor for the phase three work."
Date: November 17, 1961
Creator: Watts, H. V. & Terrell, C. W.
Partner: UNT Libraries Government Documents Department
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Fallout concentrations of 12 radionuclides in air: 1962 through mid-1964

Description: Newly developed multidimensional gamma-ray spectrometric counting techniques permit the direct measurement of twelve fallout radionuclides on air filters. Observed concentrations of Be{sup 7}, Na{sub 22}, Mn{sup 54}, Co{sup 60}, Y{sup 88}, Zr{sub 95}Nb{sup 95}, Ru{sup 106}, Sb{sup 124}, Sb{sup 125}, Cs{sup 134}, Cs{sup 137} and Ce{sup 144} during the past two and a half years help explain the origin and fallout rates of the trace radionuclides in air. 14 refs., 1 tab.
Date: June 17, 1964
Creator: Perkins, R. W.; Nielsen, J. M. & Thomas, C. W.
Partner: UNT Libraries Government Documents Department
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Thulium Oxide Irradiation

Description: Thulium oxide can be irradiated to meet the desired specific heat generation of 1.5 watts per gram as part of a flux amplification test, which will be conducted the early part of FY-1965. To obtain the heat generation level, is calculated that a 120-day irradiation will be required at a flux of 1.1 {times} 10{sup 14} neutrons/cm{sup 2}-sec. if the proposed target element is modified by reducing the thulium oxide wafer thickness from 0.080 to 0.050 inch. Also, the length of the target element sh… more
Date: April 17, 1964
Creator: Kusler, L. E.
Partner: UNT Libraries Government Documents Department
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