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Nuclear Superheat Meeting: September 1959

Description: From introduction: The Commission's underlying objective of this program is to conduct sufficient engineering and development work to determine the most feasible and economical methods of producing nuclear super-heated steam from a boiling water reactor.
Date: November 3, 1959
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report for the ML-1 Nuclear Power Plant

Description: From abstract: "Neutronic characteristics, the control and instrumentation system, equipment description and plant safety considerations of the ML-1 (mobile, low power) nuclear power plant. The site is described with reference to geology, climate, and population density."
Date: September 30, 1959
Creator: Linenberger, G. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Description: Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date: July 2, 1959
Creator: Nakazato, S.; Williams, P. M. & Wilson, W. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report

Description: From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant

Description: "This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Boiling Water Reactor Study [Part 1]: 306 Mw Power Reactor Conceptual Design

Description: From introduction: In general, the objective of this study is to provide for the development of the conceptual design criteria for the most promising type of boiling water reactor and associated complete electrical generating plant consistent with a schedule calling for start of construction in July 1960.
Date: July 1959
Creator: Ebasco Services Incorporated
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Organic Cooled Reactor Study [Part 3]: Reactor Concept Evaluation

Description: From summary and conclusions: The purpose of this volume is to present the results of design studies to select the optimum-sized electric power station utilizing an organic cooled nuclear reactor and to evaluate and optimize the various reactor concepts, with special attention to selection of the moderator, consistent with the basic design criteria established by the AEC.
Date: July 1959
Creator: Bechtel Corporation
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Report on Design Tests PR-50 and PR-51: Reactor Piping Seal Testing and Reactor Piping Structural Integrity

Description: A test program conducted to develop high integrity piping and seal components for Plutonium Recycle Test Reactor installation. Methods of preventing leakage of costly D2O coolant and maintaining operational safety were investigated.
Date: June 26, 1959
Creator: Jackson, P. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Description: Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
Date: June 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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