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Applied Health Physics Annual Report for 1963

Description: Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Date: August 1964
Creator: Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables

Description: Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Date: August 1964
Creator: Salmon, Royes
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Computer Programs Using Zonal Harmonics for Magnetic Properties of Current Systems with Special Reference to the IBM 7090

Description: Report that "discusses the magnetic vector and scalar potentials, magnetic field components and their derivatives, and flux linkage for single current systems, and the mutual inductance, forces and torques between two such systems, whose axes are coplanar but not necessarily coincident" (p. 1).
Date: December 4, 1962
Creator: Garrett, M. W.
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
open access

Design Report for Nuclear Merchant Ship Reactor Pressurized Water Loop at Oak Ridge National Laboratory Research Reactor

Description: Report describing a pressurized water loop that was constructed for use in the Maritime Reactor Program. The report also includes the operational experience of using the device. Appendices begin on page 48.
Date: 1963
Creator: Dudley, I. T.; Tidwell, D. E. & Trauger, Donald B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Development of Fabrication Procedures for Core B Fuel Elements for the Enrico Fermi Fast Breeder Reactor

Description: Report describing the "development procedures for fabricating the proposed Core B fuel element of the Enrico Fermi Fast Breeder Reactor" (p. 1). This includes a description of various components, reactor assembly, and reported conclusions. Appendices begin on page 57.
Date: 1964
Creator: Donnelly, R. G.; Thurber, W. C. & Slaughter, G. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

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.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Evaluation of an Engineering Demonstration of the Modified Zirflex and Neuflex Processes for the Preparation of Solvent Extraction Feeds from Unirradiated Zirconium-Base Reactor Fuels

Description: Report that investigates the concept of using ammonium fluoride-oxidant systems to dissolve spent U-Zr-Sn reactor fuels in both batch and continuous operation.
Date: March 1964
Creator: Kitts, F. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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