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Savannah River Project Site Report: 30,000 KW Prototype Partically Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission Idaho Operations Office

Description: Report describing a modified prototype of a nuclear reactor that uses partially uranium-enriched fuel and is cooled by helium. The construction site, site safety aspects, and design and construction costs are included.
Date: March 1959
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Partner: UNT Libraries Government Documents Department
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An Evaluation of Mercury Cooled Breeder Reactors

Description: Abstract: The technical feasibility and economic potential of fast breeder power reactor systems cooled with boiling mercury have been investigated by American-Standard under the United States Atomic Energy Commission's New Reactor Concepts Evaluation Program.
Date: October 13, 1959
Creator: Advanced Technology Laboratories
Partner: UNT Libraries Government Documents Department
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Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Description: Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design crit… more
Date: May 25, 1959
Creator: Aerojet-General Corporation
Partner: UNT Libraries Government Documents Department
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Intermediate Heat Exchanger Preliminary Design. Vol. 1, IHX Preliminary Design

Description: Preface: The intermediate heat exchanger is designed for operation in a nuclear power plant using liquid sodium as the primary and secondary coolant. Since the primary fluid coming from the reactor is radioactive, the purpose of the IHX is to transfer heat to a nonradioactive fluid which then goes to a steam generator. Because of this activity the until will be enclosed in a concrete pit and will not be accessible during periods of operation. Immediately after shut down it will be necessary … more
Date: February 28, 1959
Creator: Alco Products (Firm)
Partner: UNT Libraries Government Documents Department
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Allis-Chalmers Critical Facility: Final Safeguards Report

Description: Report discussing the final safeguards integrated into the design of the Pathfinder Atomic Power Plant for the Northern States Power Company. The plant is designed by the Allis-Chalmers Manufacturing Company in Greendale, Wisconsin. Description of the facility, operating procedures, experiments, accident analysis, safety features of the reactor, and make up of the surrounding area are included.
Date: May 1, 1959
Creator: Allis-Chalmers Manufacturing Company
Partner: UNT Libraries Government Documents Department
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Hot-Pressure Bonding of OMR Fuel Plates

Description: Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Partner: UNT Libraries Government Documents Department
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Technical Report No. 6

Description: The original melting apparatus has been converted from a one-zone to a six zone operation. Another one-zone refiner has been constructed. The experiments that have been performed to date with these two refiners are discussed in the firs two sections of this report. It is pointed out that it appears that zone melting has a limited application for the refinement of KCl and KBr. We are exploring two other means of purification: 1) ion exchange, and 2) distillation. Work on the analysis of the salt… more
Date: January 1959
Creator: Anderson, Scott
Partner: UNT Libraries Government Documents Department
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Zone Refining and Chemical Analysis of KCI and KBr Progress Report

Description: Upon initiation of our alkali halide purification program, we desired an accurate and complete chemical analysis of representative samples of the best salt commercially available. It was concluded that the most sensitive and probably most nearly complete technique is that provided by neutron activation.
Date: July 1959
Creator: Anderson, Scott; Wiley, John S. & Hendricks, Lloyd J.
Partner: UNT Libraries Government Documents Department
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Aging of Al-Li Alloys - Part I

Description: Technical report outlining experiments on aluminum-lithium alloys. From Abstract: "Aluminum-lithium alloys are subject to precipitation from solid solution, and may be age hardened by the same techniques used for more common aluminum alloys. Spherical particles of precipitate were observed with the electron microscope in 1.5% and 2.8% Al-Li alloys after aging for times comparable to those required to produce maximum hardness. Rod-shaped particles that were oriented parallel to either the (110) … more
Date: January 1959
Creator: Angerman, C. L.
Partner: UNT Libraries Government Documents Department
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Particle Accelerator Division Summary Report: April 15, 1958 through October, 1958

Description: Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.
Date: February 1959
Creator: Argonne National Laboratory. Particle Accelerator Division.
Partner: UNT Libraries Government Documents Department
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A Feasibility Study of Optically Regenerative Light Intensifier

Description: The contract was a study program to determine the feasibility of a high-gain optically-regenerative image tube. More specifically, it was a feasibility study of a close-spaced image tube which would utilize a fotoform grid to break the electron image into many independent elements. Use of the fotoform grid permits various high-gain modes of operation as the gain of the multiple-element image can be controlled or gated by the potential applied to the grid.
Date: 1959
Creator: Bain, George & Papp, G.
Partner: UNT Libraries Government Documents Department
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Control Rod Positions for Criticality. Section I. Fourth Performance. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at ambient temperature. The critical bank heights and bank worths at a coolant temperature and pressure of 130F and 400 psig were determined and are charted in the report. The test was performed after 556.6 EFPE of operation of the station.
Date: March 24, 1959
Creator: Baird, John B.
Partner: UNT Libraries Government Documents Department
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Control Rod Positions for Criticality. Section I. Third Performance. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at normal plant operating temperature and pressure. The critical bank heights and bank worths were determined for various rod combinations are charted in the report.
Date: February 12, 1959
Creator: Baird, John B.
Partner: UNT Libraries Government Documents Department
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Control Rod Positions for Criticality. Section II. Fourth Performance. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at normal plant operating temperature and pressure. The critical bank heights and bank worths were determined for various rod configurations after 560 EFPH's of reactor operations are charted in the report.
Date: March 31, 1959
Creator: Baird, John B.
Partner: UNT Libraries Government Documents Department
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Control Rod Positions for Criticality. Section II. Third Performance. Test Results DL-S-149 (T-550130)

Description: The purpose of the test was to determine critical bank heights and bank worths for various rod configurations at normal plant operating temperature and pressure. The critical bank heights and bank worths were determined for various rod combinations are charted in the report.
Date: March 24, 1959
Creator: Baird, John B.
Partner: UNT Libraries Government Documents Department
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Determination of Coefficients of Reactivity. Test Results DL-S-151 (T-550132). Section I. Fourth Performance

Description: The purpose of the test was to determine the temperature and pressure coefficients of reactivity at sere power. The value for the temperature coefficient at the operating temperature of 523 F with 556.6 EFPH plant operation was 2.5 (delta E/F) x 16(-4). The magnitude of the temperature coefficient at the plant operating temperature (523 F) indicated the reactor is very stable during normal operations. The pressure coefficient varied from values of 1.41(deltaE/psig) x 10(-6) at 1437 psig to a.57… more
Date: January 31, 1959
Creator: Baird, John B.
Partner: UNT Libraries Government Documents Department
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Reactor Automatic Control and Load Swing Tests. Test Results DL-S-144 (T-554924). Section I

Description: The purpose of this test was to determine the controlling ability of the Reactor Power and Temperature Control System and to determine the operational characteristics of the station during load swings. The Reactor Power and Temperature Control System satisfactorily controlled rod movements to maintain all primary plant parameters within their individual limits during steady state operation, ramp functions load changes and a peak xenon burnout transient. The operational characteristics of the st… more
Date: February 10, 1959
Creator: Baird, John B.
Partner: UNT Libraries Government Documents Department
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Department of Chemical Engineering Progress Report for September 1, 1957 Through June 30, 1958. Part I. Thermal Conductivity of Deuterium Oxide

Description: The thermal conductivity of heavy water was found to vary from 0.345 at 105 deg F through a maximum of 0.375 at about 265 deg F to 0.371 at 339 deg F. The conductivity was determined by a steady-state method in a cylindrical apparatus having an over-all length of 11.35 inches and a liquid layer about 0.061 inch thick. A temperature drop of approximately one degree Fahrenheit across the liquid was maintained. The temperature drop was measured with thermistors. The apparatus was calibrated with l… more
Date: October 31, 1959
Creator: Baker, B. L.
Partner: UNT Libraries Government Documents Department
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Heat Capacity & Thermodynamic Properties of Saturated Deuterium Oxide

Description: This report summarized work completed on Part II of the above contract from June 1, 1956 through June 30, 1958. Additional work, mainly calculations, was continued August 1, 1959. The heat capacity of saturated deuterium oxide has been determined between 30°C (86°F) and 200°C (392°F) by comparison methods using ordinary water as a standard. The work was divided into two temperature ranges, 30°C to 80°C and 100°C to 200°C. Somewhat different experimental techniques were employed for each range b… more
Date: September 15, 1959
Creator: Baker, B. L.
Partner: UNT Libraries Government Documents Department
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Electrochemical Studies of Hafnium, Zirconium, and Yttrium

Description: Eighth Quarterly Progress Report from the period of April 1, 1959 to June 30, 1959. Electrorefining studies have been seriously hampered during the past quarter due to recurrent air leaks into the refining cells and also due to a lack of hafnium metal for anode material.
Date: 1959
Creator: Baker, D. H.
Partner: UNT Libraries Government Documents Department
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