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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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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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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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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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Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop

Description: This report provides an overview of the creation of the Liquid Metal Fuel Reactor Experiment program. It furthers the work by constructing a single loop to test all the components required for the 16 loop reactor. This utility loop was also constructed to provide a facility for testing various components such as valves and flow meters.
Date: May 5, 1959
Creator: Baker, O. H.
Partner: UNT Libraries Government Documents Department
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Fuel Handling, Service and Waste Disposal Buildings Drain Test. Section I. Test Results DL-S-230 (T-641115)

Description: The purpose of the test was to prove the integrity of the non-active drains, the special drains, the sanitary drains, the chemical waster drains and the storm water drains by means of a water flow test and visual inspection. The two roof boxes and the one floor drain of 1B Auxiliary Equipment Room did not drain properly. The lab sink in the west end of the Radiochemistry Lab drained to the Special Monitored West Transfer Tank instead of the Monitored Waster Transfer Tank. All other drains funct… more
Date: March 31, 1959
Creator: Barclay, Richard E.
Partner: UNT Libraries Government Documents Department
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Periodic Radiation Survey. Section II. First Performance. Test Results DL-S-231, T-612394

Description: The purpose of the test was to determine the radiation level in the Turbine-Governor Service Building, around the Fuel Handling Canal and in the limited access areas of the reactor plant containers during plant operation. All radiation levels were background level readings except for a few points above background located in the walkway areas going from the auxiliary chamber into the reactor chamber, boiler chamber and pressurizer compartment. The only neutrons detected were slow neutrons in th… more
Date: March 5, 1959
Creator: Barclay, Richard E.
Partner: UNT Libraries Government Documents Department
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Present Status of Semiconductor Particle Counters

Description: This review lists some of the salient features of semiconductor particle counters and cannot claim to contain an exhaustive listing of all the work in the field. Performance results on the surface-barrier counters as developed at California Institute of Technology are included as typical for this type of counter, though comparable results have been obtained elsewhere.
Date: November 23, 1959
Creator: Barnes, C. A.
Partner: UNT Libraries Government Documents Department

[Illustrations: Figures 1-10]

Description: Maps and charts illustrating aspects of a photogeologic reconnaissance study of the spatial relationship of uranium deposits to structure and stratigraphy in Duval County, Texas.
Date: February 1959
Creator: Barnes, John C.
Partner: UNT Libraries Government Documents Department
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