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Plutonium Recycle Critical Facility: Final Safeguards Analysis

Description: Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Date: February 1962
Creator: Anderson, J. K. & Winegardner, W. K.
Partner: UNT Libraries Government Documents Department
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Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions

Description: Abstract: The MSAR corrosion test loop was used to study the effect of VKE-shaped crevices on the corrosion resistance of Zircaloy under boiling heat-transfer condtions in both ammoniated and lithiated water at pH 10.5.
Date: April 1962
Creator: Anderson, W. Kermit & McGoff, M. J.
Partner: UNT Libraries Government Documents Department
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Salt Bath Heat Transfer Rates for Uranium Plate

Description: Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date: February 1, 1962
Creator: Burditt, R. B.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

Description: First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
Date: April 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies

Description: Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).
Date: March 1962
Creator: Combustion Engineering, inc. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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Thermal Conductivity of UO2

Description: Report discussing the thermal conductivity of uranium dioxide. The first part of the report includes the thermal effects on the substance's physical form, while the second part describes the experimental details.
Date: September 1962
Creator: Daniel, J. L.; Matolich, J., Jr. & Deem, H. W.
Partner: UNT Libraries Government Documents Department
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Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1

Description: Report describing the evaluation of the effects of irradiation on a high pressure water loop that ruptured while testing fuel elements. Includes photographs of the damaged tube as well as chemical analyses.
Date: December 1962
Creator: Defferdin, L. J.
Partner: UNT Libraries Government Documents Department
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Pulse Amplifier Manual

Description: Manual for the use and repair of repair pulse amplifiers. This covers general testing routines, specific tests, and a bibliography of related materials.
Date: 1962
Creator: Fairstein, E.
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.
Partner: UNT Libraries Government Documents Department
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Annual Progress Report on Fuel Element Development for Fiscal Year 1961

Description: Report that reviews the yearly progress made in Reactor Fuel and Materials Development Program at the Engineering Test Reactor (ETR) and Materials testing reactor (MTR).
Date: March 9, 1962
Creator: Gibson, G. W. & Shupe, O. K.
Partner: UNT Libraries Government Documents Department
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Facility For Photographing in-Pile Meltdown Experiments in TREAT

Description: Report regarding the fabrication of a transparent meltdown facility for the purpose of photographing simulated meltdowns.
Date: January 1962
Creator: Golden, G. H.; Dickerman, C. E. & Robinson, L. E.
Partner: UNT Libraries Government Documents Department
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MUFT Revision : A Fast Neutron Spectrum Code for the IBM-650

Description: Report documenting the MUFT-R program, which is "designed to solve the fast neutron transport problem for general mixtures of elements and obtain sets of average fast neutron diffusion constants for specified portions of the fast energy spectrum" (p. iii). Includes detailed derivations of utilized equations.
Date: 1962
Creator: Grimesey, Robert A.; Mullen, Frank Edward & Gannon, L. J.
Partner: UNT Libraries Government Documents Department
open access

Experimental Breeder Reactor-II (EBR-II) Shield Design

Description: Report describing the EBR-II shield and the methods employed in arriving at the final design. The major shield design problems for that reactor are enumerated and discussed.
Date: September 1962
Creator: Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
Partner: UNT Libraries Government Documents Department
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