Review of the Corrosion Product Radioactivity Program at the Army Package Power Reactor : Alco R & D report (open access)

Review of the Corrosion Product Radioactivity Program at the Army Package Power Reactor : Alco R & D report

Abstract: An analysis and a summary are.given of the radioactivity buildup program at the Army Package Power Reactor during the last nine months. · Due to the wide fluctuation of water and crud results, only general interpretations can be made with this data. Metal test coupon data indicate a substantially greater buildup on Croloy 16-1 metal than on Type 304 stainless steel. Coupled with the decreased ability to remove the radioactivity buildup on Croloy 16-1 by conventional descaling techniques, the implication is that this metal might pose a serious problem for use as steam generator material. It was emphasized, however, that results to date ae only preliminary and extensive additional experimentation would be required to reach more definite conclusions.
Date: April 25, 1958
Creator: Medin, A. L.
System: The UNT Digital Library
Theory of Asymmetric Arrays of Control Rods in Nuclear Reactors (open access)

Theory of Asymmetric Arrays of Control Rods in Nuclear Reactors

Introduction: Seldom does the actual arrangement of control elements in a nuclear reactor confers to the ideal and convenient mathematical array. In order to achieve shim control. safety and regulation, it is desirable to design with rods of different sizes and materials. With given fuel element arrangement, typically in square or hexagonal lattice spacing, there will be rods located at different distances form the center of the core and from each other. As the reactor operates, absorbers will be withdrawn, leaving further asymmetries in the location of those remaining. It is the purpose of this report to develop in detail a two-group diffusion theory with as complete generality as possible. The method is as yet restricted to the unreflected core, or to the reflected core by use of reflector savings and bare equivalent geometries.
Date: April 25, 1959
Creator: Murray, Raymond L.
System: The UNT Digital Library
Hazards Summary Report for the Battelle Research Reactor (open access)

Hazards Summary Report for the Battelle Research Reactor

From summary: "This report was prepared for the Advisory Committee on Reactor Safeguards for their review and consideration of the potential hazards concerning the Battelle Memorial Institute Research Reactor."
Date: April 4, 1955
Creator: Chastain, J. W.; Redmond, R. F.; Klickman, A.; Anno, J. & Fawcett, S. L.
System: The UNT Digital Library
Preliminary Economic Report on the Application of Atomic Power to Merchant Ships (open access)

Preliminary Economic Report on the Application of Atomic Power to Merchant Ships

Discussion of the economic considerations for atomic power in merchant ship propulsion.
Date: April 1956
Creator: Burns, William J.
System: The UNT Digital Library
Preliminary Economic Report on the Application of Atomic Power to Merchant Ships. Part 2. Oil Tanker Ships (open access)

Preliminary Economic Report on the Application of Atomic Power to Merchant Ships. Part 2. Oil Tanker Ships

Discussion of the economic considerations for atomic power in merchant ship propulsion.
Date: April 1956
Creator: Burns, William J.
System: The UNT Digital Library
Floating-Decimal Matrix Inversion (open access)

Floating-Decimal Matrix Inversion

Use of Crout Method in floating-decimal notation in IBM Model I Card-Programmed Calculator.
Date: April 1955
Creator: Trantham, F. M., Jr.
System: The UNT Digital Library
Preliminary Investigations for an Advanced Engineering Test Reactor: Addendum (open access)

Preliminary Investigations for an Advanced Engineering Test Reactor: Addendum

More detailed study of an advanced engineering test reactor.
Date: April 16, 1957
Creator: Leyse, C. F. & Leonard, B. H., Jr.
System: The UNT Digital Library
Engineering Study on Underground Construction of Nuclear Power Reactors (open access)

Engineering Study on Underground Construction of Nuclear Power Reactors

Engineering study on underground construction of nuclear power reactors.
Date: April 15, 1958
Creator: Beck, Christian
System: The UNT Digital Library
Uranium Production - Process Designs for Leached Zone Plants Volume 3. Alumina Recovery Section (open access)

Uranium Production - Process Designs for Leached Zone Plants Volume 3. Alumina Recovery Section

Processing of Florida leached zone material for the recovery of alumina.
Date: April 13, 1955
Creator: Clements, D. F.; Williams, W. B.; McCullough, R. F. & Wrege, E. E.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment, Quarterly Technical Report: April 1958 - June 1958 (open access)

Liquid Metal Fuel Reactor Experiment, Quarterly Technical Report: April 1958 - June 1958

Quarterly technical report discussing progress and activities of the Liquid Metal Fuel Reactor Experiment.
Date: April 1958
Creator: Babcock & Wilcox Company
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment: Quarterly Technical Report, April-June, 1959 (open access)

Liquid Metal Fuel Reactor Experiment: Quarterly Technical Report, April-June, 1959

Liquid Metal Fuel Reactor Experiment program quarterly technical report.
Date: 1959-04/1959-06
Creator: unknown
System: The UNT Digital Library
Filtration of Radioactive Aerosols by Glass Fibers: Part Two -- Appendices (open access)

Filtration of Radioactive Aerosols by Glass Fibers: Part Two -- Appendices

From introduction: "Five appendices, each of which pertains to a separate phase of the Filtration of Radioactive Aerosols by Glass Fibers program."
Date: April 16, 1951
Creator: Blasewitz, A. G.; Carlisle, R. V.; Judson, B. F.; Katzer, M. F.; Kurtz, E. F.; Schmidt, W. C. et al.
System: The UNT Digital Library
The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium (open access)

The Purex process : a Solvent Extraction Reprocessing Method for Irradiated Uranium

Purex process which utilizes solvent extraction to separate and purify uranium and plutonium from each other and from fission products contained in irradiated uranium fuel elements.
Date: April 8, 1957
Creator: Irish, E. R. & Reas, W. H.
System: The UNT Digital Library
The Relative Thermal Conductivities of Liquid Lithium, Sodium, and Eutectic NaK, and the Specific Heat of Liquid Lithium (open access)

The Relative Thermal Conductivities of Liquid Lithium, Sodium, and Eutectic NaK, and the Specific Heat of Liquid Lithium

Report discussing the relative thermal conductivities of liquid lithium, sodium, and eutectic NaK, and the specific heat of liquid lithium, as well as the methods and materials used to determine this information.
Date: April 21, 1950
Creator: Yaggee, F. L. & Untermyer, Samuel, 1912-
System: The UNT Digital Library