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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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Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions

Description: Theoretical investigation on the nature of ion exchange of acidified uranyl sulfate solutions with Dowex 21K, a strong base ion exchange resin.
Date: September 28, 1962
Creator: Stein, P. E.
Partner: UNT Libraries Government Documents Department
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A Technical and Economic Evaluation of Solid-Fuel Gasification using Nuclear Heat: Production of Pipeline Gas, Liquid Fuels, and Chemicals from Lignite and Bituminous Coal

Description: From abstract: Results are reported of a study to determine the most economical method of utilizing nuclear heat to gasify a North Dakota lignite and a West Virginia bituminous coal so that the resulting gas is suitable as a source of synthesis gas for fuels and chemicals.
Date: November 30, 1962
Partner: UNT Libraries Government Documents Department
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Special Power Excursion Reactor Test III Pressurizer Vessel Failure

Description: Report documenting results of a study of the cause of failure at the SPERT III reactor facility.
Date: January 29, 1962
Creator: Heffner, R. E.; Wilson, T. R.; Halls, D. P.; Hickman, W. W. & Hoopingarner, K. R.
Partner: UNT Libraries Government Documents Department
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Health Physics Division Annual Progress Report, July 31, 1962

Description: Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date: 1962
Creator: Oak Ridge National Laboratory. Health Physics Division.
Partner: UNT Libraries Government Documents Department
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Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1962 - June 1, 1962

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: July 1, 1962
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Partner: UNT Libraries Government Documents Department
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Maritime Reactor Project Annual Progress Report, November 30, 1961

Description: Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1961 are presented. This report includes tables, illustrations, and photographs.
Date: 1962~
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
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Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962

Description: Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress are presented. This report includes tables, illustrations, and photographs.
Date: 1962
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
open access

Supplement to Reactor Containment Design Study

Description: Summary: Report SL-1868 is a technical and economic feasibility study of four containment methods, i.e., standard containment, pressure relief, pressure supression and low pressure containment, for 44 MWe direct cycle and 180 and 300 MWe dual cycle boiling water reactor plants.
Date: April 23, 1962
Creator: Johnson, R. A. & Nelson, I.
Partner: UNT Libraries Government Documents Department
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Reactor Technology Report Number 22: Chemistry

Description: Quarterly report issued by the Knolls Atomic Power Laboratory to report to the industry on developments in unclassified reactor technology. This issue focuses on chemistry information.
Date: September 1962
Partner: UNT Libraries Government Documents Department
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