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A Conceptual Study of a 100 kw Gas Cooled Reactor Power Plant for a Remote Location

Description: From introduction: This report details the conceptual design of a 100 kw gas cooled reactor power plant of the type that would satisfy the electrical and space heating load of the Air Force distant early warning stations and might find application at other remote bases.
Date: May 31, 1955
Creator: Frankfort, J. H. & Thompson, W. I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas Cooled Nuclear Reactor Study

Description: Study of a gas cooled reactor with design specifications providing for a source of high temperature heat to a stream of helium. This reactor, in turn, is used as a source of heat for the air stream in a gas-turbine power plant.
Date: July 31, 1956
Creator: Thompson, A. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Gas-Cooled Marine Nuclear Power Plant: Interim Report. Project 16

Description: From preface: The principal portion of this report is the scientific and engineering description of a novel reactor and power-plant scheme which was proposed by General Atomic in response to an invitation of the Maritime Administration.
Date: January 25, 1957
Creator: Thompson, W. I.; Adler, F.; Case, K.; Bond, W. H.; Creutz, E. C.; Hale, E. A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of Reactor Core Materials for a Gas-Cooled Reactor Experiment

Description: From introduction: "On February 1, 1956, Batelle was awarded a contract by the Army Reactor Branch (ARB) to select, develop, and test core materials which could be used successfully in conducting a Gas Cooled Reactor Experiment (GCRE). The prime objective of the GCRE would be to evaluate small portable reactor systems for military application...The present report is concerned with the GCRE activities at Batelle during approximately the 7 months' period following the first report of this series,… more
Date: July 11, 1957
Creator: Keller, Donald L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Appendix to Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office

Description: Report containing documentation of projects undertaken by the multiple branches of the Health and Safety Division of the Idaho Operations Office at the Nuclear Reactor Testing Station (NRTS).
Date: March 1958
Creator: U.S. Atomic Energy Commission. Idaho Operations Office.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility Study, 44,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optium Power Plant) for United States Atomic Energy Commission, Idaho Operations Office

Description: Report that "contains a discussion of the feasibility study and cost estimates for a gas cooled, partial enriched uranium, graphite moderated power plant" (p. 3).
Date: April 1, 1958
Creator: Kaiser Engineers
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office

Description: Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office

Description: Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Design 55,000 KW Prototype Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype for an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office

Description: Report describing the preliminary design of a 55,000 kW prototype of a natural uranium nuclear power plant for the United States Atomic Energy Commission. Testing of the design and potential requirements for operating the plant are included.
Date: April 1, 1958
Creator: Kaiser Engineers
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Survey of Non-Fuel-Bearing Materials for the Marine Gas-Cooled Reactor

Description: Results of an initial examination of non-fuel-bearing materials for the Marine Gas Cooled Reactor are presented. Areas given specific attention include structural and cladding materials and graphite moderator. Other areas not included because of classification include zirconium hydride moderator and control materials. In each report section, available pertinent information is summarized and a plan for future work is given.
Date: May 1, 1958
Creator: Bokros, J. C.; Dijkstra, L; & Merten, U.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Comparison of Optimum Natural Uranium Nuclear Power Plant and Optimum Enriched Uranium Nuclear Power Plant

Description: Report that "compares the designs of an optimum natural uranium power plant and an optimum partially enriched uranium power plant, both using CO2 as a coolant" (p. 1). Includes a description of each plant's design, construction, and economic considerations.
Date: August 1958
Creator: Kaiser Engineers
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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GCRE Critical-Assembly Studies

Description: This report follows critical-assembly studies made to provide engineering and physics data to aid in developing the Gas Cooled Reactor Experiments.
Date: September 10, 1958
Creator: Dingee, David A.; Ballowe, William C.; Klingensmith, Raymond W.; Egen, R. A.; Jankowski, Francis J. & Chastain, Joel W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Further Studies with the GCRE Critical-Assembly

Description: This report follows ciritical-assembly studies on: the effect on reactivity caused by changes in axial reflector materials; the effect on reactivity and the power perturbation caused by fast safety control-blade guides; the effect of changes in fuel-element material composition; the effect of changes in fuel-elements spacing designed to produce uniform radial power-generation rates.
Date: December 29, 1958
Creator: Dingee, David A.; Ballowe, William C.; Egen, R. A.; Jankowski, Francis J. & Chastain, Joel W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Canning graphite for gas-cooled reactors

Description: From abstract: "A preliminary investigation was made of techniques and materials for canning graphite to protect it for use at high temperatures in a nitrogen-oxygen atmosphere"
Date: 1959
Creator: Paprocki, Stan J.; Carlson, Ronald J. & Bonnell, Paul H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Helium Cooled Loop in the GETR

Description: The General Electric Test Reactor (GETR) facility is designed to irradiate the fuel specimens in a helium-cooled environment at 800 degree F and pressures from 315 to 400 psig. Thermal neutron fluxes in the fuel are of the order of 3 x 10(13) mv and the induvial test pieces, of which there are three in each facility tube, generate five kilowatts at heat fluxes slightly over 200,000 Btu per hour per square foot. Five facility tubes are provided in the reactor pool. Separate coolant lines are bro… more
Date: 1959
Creator: Hausman, R. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ Fuel Elements

Description: "The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those pro… more
Date: 1959
Creator: Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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