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PATHFINDER ATOMIC POWER PLANT STEAM SEPARATOR DEVELOPMENT

Description: Development of a steam separator the Pathfinder Reactor is reported. A full-scale separator model was developed through the combination of scale-model testing and the application of principles associated with the existing theory of centrifugal separation. This model was put through full-scale air-water tests which led to modifications and a final design which meets Pathfinder requirements. Design data are included for the reactor and the steam separator. (J.R.D.)
Date: June 15, 1962
Creator: Kutsch, G. C.; Swanson, D. H. & Yant, H. W.
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL INVESTIGATION OF THE EFFECTS OF ULTRASONIC VIBRATIONS ON BURNOUT HEAT FLUX WITH BOILING WATER. Quarterly Technical Progress Report No. 3, April-June 1961

Description: The heat-transfer loop was completed and is in operation. Difficulty was experienced in obtaining a sufficiently strong connection between the burnout- detector voltage tap and the heating element. This problem and its potential solution are described. The lack of means of obtaining controlled burnout prevented collection of data on the burnout effects of the ultrasonic field. (auth)
Date: October 31, 1962
Creator: Romie, F.E.
Partner: UNT Libraries Government Documents Department
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HYDROLOGIC AND GEOLOGIC STUDIES FOR PROJECT GNOME. Preliminary Report

Description: Geologic lnformation required to define the pre- and post-shot physical and chemical characteristics of the sait and other rocks affected by the exploslon was gathered. Information on the pre- and post-shot hydrologic condltlons at the site and the surrounding area was also obtalned. (M.C.G.)
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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RADIOISOTOPES AND RADIATION APPLICATIONS. Quarterly Progress Report No. 12

Description: Continued research is reported in the areas of intrinsic radioactive tracers for industrial process control and the effects of structural factors on radioinduced graft polymerization. The use of Be-- Po neutron sources for production of short-lived isotopes is being investigated. Data are included on the effects of target volume, high-Z scattering media, target-isotope concentration, and macroscopic cross-section on speciflc and total activation produced with a 10-curie source. Research on graf… more
Date: April 18, 1962
Creator: Sunderman, D.N. ed.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant Technical Progress Report, January 1962-March 1962

Description: S>Progress is reported on the research and development program being performed in connection with the design of the Pathfinder Atomic Power Plant. The topics covered include: fuel material cladding, bonding, and irradiation testing; heat transfer and fluid flow; fuel element manufacturing research and development; low-enrichment superheater fuel element design; mechanical studies of control rods, guide tubes, and control rod drives; reactor physics; and reactor and system dynamics. (C.H.)
Date: June 30, 1962
Partner: UNT Libraries Government Documents Department
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Stress and Deflection of Boiler Fuel Element Boxes

Description: Equations were derived by strain-energy methods for analyzing the stress and deflection in the boiler fuel element boxes used in the Pathfinder nuclear reactor. These boxes are of two types, both constructed of Zircaloy lI. One box is approximately 5 in. sq. The second is approximately 10 1/2 in. sq divided internally into four compartments (5 in. sq) by a cruciform control-rod guide structure. Stress and deflection in the box walls are caused by pressure differences across the walls. The equat… more
Date: April 13, 1962
Creator: Vlies, L. E.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant Analog Simulator.

Description: The steady-state and dynamlc characterlstics of the Pathfinder systems were simulated on a dual-console Pace Analog Computer. The derivation of the system equations, the assumptions involved, their numerical evaluation, and their conversion to analog circuitry are described. The Pathfinder system is unique because of the internal nuclear superheater, and controlled, forced recirculation. In simulating this system the following major assumptions were maden the reactor is a boiling-water type; mo… more
Date: January 31, 1962
Creator: Crimmins, D. H.; Mohr, D. & Stone, J. T.
Partner: UNT Libraries Government Documents Department
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IN-PILE GAS-COOLED FUEL ELEMENT TEST FACILITY

Description: Paper presented at American Nuclear Society Meeting, June I8-21, 1962, Boston, Mass. Design and operating problems of unclad and ceramic gas-cooled reactor fuels in high temperature circulating gas systems will be studied using a test facility now nearing completion at the Oak Ridge Research Reactor. A shielded air-tight cell houses a closed circuit gas system equipped for dealing with fission products circulating in the gas. Experiments can be conducted on fuel element performance and stabilit… more
Date: July 10, 1962
Creator: Zasler, J.; Huntley, W. R.; Gnadt, P. A. & Kress, T. S.
Partner: UNT Libraries Government Documents Department
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Pathfinder Atomic Power Plant. Thermal and Hydraulic Design of the Pathfinder Boiling Water Integral Nuclear Superheating Reactor

Description: A thermal and hydraulic design investigation of the Pathfinder Reactor, including analytical and experimental determinations, as well as a complete set of performance calculations, was carried out. A detailed analysis of the reactor energy balance was conducted. Results of the analyses indicated that the reactor will perform within the limits of the material design criteria and operational requirements. Fuel element temperatures are not excessive under the worst combination of circumstances. Th… more
Date: August 29, 1962
Partner: UNT Libraries Government Documents Department
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BOILING NUCLEAR SUPERHEATER (BONUS) POWER STATION. Supplementary Study. Extrapolation to Large Central Station Integral Nuclear Superheat Plant

Description: An evaluation was made of the maximum size plant for which the BONUS reactor plant could serve as a realistic prototype and the design changes required to increase the size and characteristics for the present BONUS design such that it could serve as a realistic prototype for the largest feasible integral-superheat reactor power plant. (M.C.G.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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Radiochemical Processing-Off-Site Transportation and Ultimate Storage Problems

Description: Safe and economic methods of handling radioactive materials off-site are required for the successful operation of nuclear chemical plants. These occasions arise in the shipment of spent fuel, radioactive, isotopes, and liquid wastes. An unsolved problem exists in the development of techniques and sites for the final disposal of waste products. (auth)
Date: March 14, 1962
Creator: Blomeke, J. O. & Shappert, L. B.
Partner: UNT Libraries Government Documents Department
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MODIFICATION OF THE EXPERIMENTAL BOILING WATER REACTOR (EBWR) FOR HIGHER- POWER OPERATION

Description: Supplement to ANL-5607. Alterations and additions made to the Experimental Boiling Water Reactor (EBWR) plant to permit operation at power levels up to I00 Mw(t) are described. Topics covered include over-all system modifications and additions, nuclear component modifications and additions, and reboiler plant component description. (M.C.G.)
Date: April 1, 1962
Creator: Matousek, J.F. comp.
Partner: UNT Libraries Government Documents Department
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Tests of a Vapor-Space Feed Nozzle for Calcining Aluminum Nitrate Solutions in a Fluidized Bed

Description: An investigation was conducted to determine the performance of a vapor- space feed nozzle which sprayed aluminum nitrate solution on the surface of a fluidized bed calciner. Results indicate that this type of feed system is satisfactory for calcining aqueous wastes from the processing of spent aluminum- type nuclear fueIs. Process and product control were achieved by adjusting the volumetric ratio of the air to the liquid fed to the nozzIe. The results obtained at various operating conditions a… more
Date: October 31, 1962
Creator: Lohse, G. E.
Partner: UNT Libraries Government Documents Department
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INVESTIGATION OF THE TECHNICAL FEASIBILITY OF COLD EXTRUSION FOR ZIRCALOY-2 TUBING PRODUCTION. Quarterly Technical Progress Report, October-December 1960

Description: S>Activities included completion of room-temperature extrusion tests on Zircaloy bar, and extrusions with 50% reduction at temperatures up to 400 deg C. Results of these tests are tabulated along with results of billet piercing tests at 300 deg C. It is noted that production of capped Zircaloy tubes by cold extrusion appears promising. (J.R.D.)
Date: October 31, 1962
Partner: UNT Libraries Government Documents Department
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Radiochemistry of uranium

Description: This volume which deals with the radiochemistry of uranium is one of a series of monographs on radiochemistry of the elements. There is included a review of the nuclear and chemical features of particular interest to the radiochemist, a discussion of problems of dissolution of a sample and counting technique, and finally, a collection of radiochemical procedures for the element as found in the literature.
Date: March 1, 1962
Creator: Gindler, J.E.
Partner: UNT Libraries Government Documents Department
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THE SNAP II POWER CONVERSION SYSTEM TOPICAL REPORT NO. 9, ALTERNATOR ANALYSIS, DESIGN AND DEVELOPMENT

Description: The 3 kw nuclear auxiliary power unit deslgnated SNAP II is intended for use in a satellite vehicle. The system consists of a reactor heat source, a mercury Rankine engine, and a permanent magnet alternator. The design details, test results, and development of the SNAP lI alternator are presented. (auth)
Date: October 31, 1962
Creator: Bucklin, R.L.; Galysh, J.W. & Morgan, H.J.
Partner: UNT Libraries Government Documents Department
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RADIOISOTOPE AND RADIATION APPLICATIONS. Quarterly Progress Report No. 13

Description: Research was continued during the report period on the use of isotope neutron sources for producing short-lived radioisotopes. Experiments with a newly constructed betacounting cell are reported in which a 50-curie Be--Po neutron source was used. Study of the radiation chemistry of polymers was continued concerning the effects of polymer structure on free-radical formation. Free-radical formation in several additional polymers was studied. Preliminary work is also reported in an investigation o… more
Date: July 19, 1962
Creator: Sunderman, D.N. ed.
Partner: UNT Libraries Government Documents Department
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INVESTIGATION OF THE TECHNICAL FEASIBILITY OF COLD EXTRUSION FOR ZIRCALOY-2 TUBING PRODUCTION. Quarterly Technical Progress Report No. 3, April-June 1961

Description: Investigations are being made to establish the feasibility of using cold extrusion to produce Zircaloy-2 tubular products. Tests on extruding 1 1/4-in. diameter billets were completed. Samples in 46 bar-extrusion tests were extruded with 80% reduction at 400 deg C. Severe lubricant breakdown occurred. Piercing tests were conducted at, room temperature and 200 deg C, using 50% reduction and a 140-degree conical punch profile. Good extrusions were obtained in forraing 1.07-in. OD x 0.052-in. wall… more
Date: October 31, 1962
Creator: Weil, F.E. & Hill, J.G.
Partner: UNT Libraries Government Documents Department
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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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The Development and Testing of UO2 Fuel Systems for Water Reactor Applications: Summary Report, July 1, 1961 - June 15, 1962

Description: From introduction: "The work described in this report represents the Joint United States - European Atomic Energy Community effort which is in keeping with the spirit of cooperation in contributing to the common good by the sharing of scientific and technical information and minimizing the duplication of effort by the limited pool of technical talent available in Western Europe and the United States."
Date: June 1962
Creator: Murtha, B. E. & Chernock, W. P.
Partner: UNT Libraries Government Documents Department
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