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Status Report on the Disposal of Radioactive Wastes

Description: The new and as yet unsolved problems introduced by the production of large quantities of fission products and radioactive isotopes from fission or neutron capture present mankind a most complex technical, economic, and political problem. On one hand, the possibility of using the fission process to produce energy from an unexploited and abundant natural source is emerging from large programs of research and development. We are also beginning to see the promise of use of particulate and electroma… more
Date: June 25, 1957
Creator: Culler, Floyd L., Jr. & McLain, Stuart
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Instructions for the Operation of an ORACLE Code for a Monte Carlo Solution of the Transport Problem for Gamma Rays Incident Upon a Slab

Description: A program has been coded for the ORACLE which will solve, using Monte Carlo technique, the transport problem for monodirectional, monoenergetic gamma radiation incident at an angle Θ, upon an infinite laminated slab of finite thickness. Each of the laminations (or regions) is itself an infinite, homogeneous slab of finite thickness. The code is designed to give estimates of energy deposition, energy flux, tissue dose rate, reflected and transmitted energy current, and the angular and energy dis… more
Date: October 26, 1960
Creator: Aulender, S. & Trubey, D. K.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Comparative Evaluation of Advanced Converters

Description: Report issued by the Oak Ridge National Laboratory discussing advanced converters. Comparisons of advanced converters are presented. This report includes tables, and illustrations
Date: January 1965
Creator: Rosenthal, M. W.; Adams, R. E.; Bennett, L. L.; Carter, W. L.; Douglas, D. A., Jr.; Hoskins, R. E. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Testing of Fuel for Core B of the Enrico Fermi Fast Breeder Reactor

Description: Report issued by the Oak Ridge National Laboratory discussing irradiation testing of fast breeder reactors. As stated in the introduction, "it is the purpose of this report to describe the irradiation studies carried out in support of the Core B fuel element development program" (p. 3). This report includes tables, illustrations, and photographs.
Date: November 1964
Creator: Thurber, W. C.; McQuilkin, F. R.; Long, E. L., Jr. & Osborne, M. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Snap-8 Corrosion Program Quarterly Progress Report for Period Ending November 30, 1964

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Snap-8 Corrosion Program. Progress in design, operation, and experimental work is presented. This report includes tables, illustrations, and photographs.
Date: March 1965
Creator: Savage, H. W.; Compere, E. L.; MacPherson, R. E.; Huntley, W. R. & Taboada, A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy

Description: Report documenting the corrosion of fluorinators of the Oak Ridge National Laboratory's volatility pilot plant. Includes descriptions of the fluorinators, their operating environments, and the results of their corrosion.
Date: March 1965
Creator: Youngblood, E. L.; Milford, R. P.; Nicol, R. G. & Ruch, J. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Monte Carlo Estimation of the High Energy Neutron Flux Distribution in the ORNL Graphite Reactor

Description: The flux through a given region is proportional to the total lengths of the neutron flight paths that intersect that region. The analytical Monte Carlo procedure manufactured neutron flight paths and totaled the lengths of all paths intercepted by the regions illustrated in Figure 1. The procedure was designed to utilize the various symmetries in the lattice. / Consider a portion of the lattice whose planar cross-section is shown in Figure 5. If R is the region in which the flux is to be estima… more
Date: February 23, 1955
Creator: Moshman, Jack
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Report of the Solution Corrosion Group for the Period Ending April 30, 1957

Description: A third test of the mockup of the Zircaloy - stainless steel transition joint as used in the HRT reactor vessel was completed. No additional mechanical deflections of the bellows were made, but 12 additional thermal cycles of the unit were carried out. . The joint and bellows functioned properly and were leak-tight. Corrosion of stainless steel in 0.04 m UO2SO4 containing equimolar beryllium sulfate was not greater at 10-15 fps and much less at 15-75 fps, than in HRT solution at 200 and 225 C. … more
Date: April 30, 1957
Creator: Griess, J. C.; Savage, H. C.; English, J. L.; Greeley, R. S.; Buxton, S. R.; Hess, D. N. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Ninth Quarter, July-September 1961

Description: From introduction: "This is the ninth 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: June 1962
Creator: Pennington, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Suggested Fabrication Procedures for Zircaloy-2 Mill Products in Ingot Quantities

Description: Suggested fabrication procedure for Zircaloy-2 sheet, plate, rod, and bar are presented. These procedures are based upon the best present knowledge of the physical and mechanical metallurgy of Zircaloy-2 and are designed to produce material with a minimum amount of preferred orientation, anisotropy of mechanical properties, and intermetallic stringers. The recommended procedures cover ingot soaking fabrication, heat treatment, finish, workmanship, identification, and inspection.
Date: unknown
Creator: Picklesimer, M. L. & Rittenhouse, P. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Simple Quasi Reference Electrode … Applications in Controlled-Potential Polarography and Voltammetry and in Chronopotentiometry

Description: The quasi reference electrode ( Q.R.E. ) is a bright platinum wire or other inert conductor immersed directly in the solution; it may have a very small area. It is used instead of a true reference electrode but must be used with potentiostatic or other circuits that prevent the drawing of cell current through the Q.R. E. When used in appropriate situations, the results obtained by use of a Q.R.E. are like those obtained with a true reference electrode except for the lack of thermodynamic meanin… more
Date: July 1964
Creator: Fisher, D. J.; Belew, W. L. & Kelley, M. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Nuclear Superheat Quarterly Project Report: Eleventh Quarter, January-March 1962

Description: From introduction: "This is the eleventh 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: August 1962
Creator: Pennington, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Fourteenth Quarter, October-December 1962

Description: From introduction: "This is the fourteenth in 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: January 15, 1963
Creator: Pennington, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Superheat Quarterly Project Report: Twelfth Quarter, April-June 1962

Description: From introduction: "This is the twelfth 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: March 1963
Creator: Pennington, R. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Electromagnetic Research Division Quarterly Progress Report, Part I for Period Ending March 31, 1952

Description: From abstract: "Relocation of the ion source in the 86-inch cyclotron has increased the available beam energy substantially. Modifications have also been made to permit the use of targets of 100 square inches. Proton currents of one milliampere can now be obtained readily at ~24 Mev. The 63-inch cyclotron has been completely assembled and checked. In rf tests a 75 kv dee-to-dee voltage has been maintained, under vacuum, for long periods without evidences of failures, thus exceeding the 60 kv de… more
Date: 1952
Creator: Livingston, Robert S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Determination of the Nil-Ductility-Transition Temperature for A212B Steel Used in the N. S. Savannah Pressure Vessel

Description: The nil-ductility-transition (NDT) temperature, as defined by the Naval Research Laboratory drop-weight test, was determined on the A212B carbon-silicon steel used in the pressure vessel of the N. S. Savannah nuclear reactor. Correlations were made with the Charpy-V-notch impact energy at NDT. Specimens taken at two different thickness location from materials used in the upper closure head of the reactor vessel yielded NDT temperatures of 0 - 20°F which correspond to Charpy-V-notch impact energ… more
Date: July 23, 1959
Creator: Thurber, W. C. & Lamartine, J. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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