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Fuel Cycle Program: A Boiling Water Reactor Research and Development Program - First Summary Report, March 1959-July 1960

Description: The Fuel Cycle Development Program is a basic development program of boiling and other water reactor technology. This is the first report to the U.S. Atomic Energy Commission of activities carried out under this program. It constitutes a review of the progress from April 27, 1959 through July 31, 1960.
Date: 1960
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Compact Control Rod Drive Study For a Boiling Water Reactor in a T7 Tanker

Description: The reason for initiating the compact drive study for the T7 tanker was to investigate control rod drive size, location, and removal space requirement factors and select the control rod drive mechanism which would allow optimization of the over-all size of the containment vessel. Approximately twelve mechanical/hydraulic control rod drive arrangements were considered during this study.
Date: August 8, 1960
Creator: Biglieri, N. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Report: 300 KWe Capsule Nuclear Power Plant Study

Description: This report describes progress made in the study of the feasibility of the concept, plant arrangement studies, and considerations pertaining to partial plant attendance. It is concluded that both the indirect and direct boiling cycles are feasible. The recommended reference design is the direct cycle, in a single capsule, with the turbine, generator and pumps on a single shaft.
Date: June 30, 1960
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Further Experimental Results on Natural Circulation Loop Performance at 1000 psia Under Periodic Accelerations

Description: Experimental results on the effect of periodic acceleration on a natural circulation, 1000 psia, two-phase flow loop are presented, and related to the topic of marine reactor design. The initial results of this work were given previously in GEAP 3397.
Date: October 24, 1960
Creator: Quinn, E. P.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Report Chicago Operations Office Steam Separation Program, February-March, 1960

Description: A program of free-surface steam-water separation at 600 psig was carried out in support of the design for operation of the Experimental Boiling Water Reactor at 100 MW thermal. Reduced test data are presented without evaluation since the ANL technical representative received an original copy of the data for evaluation with respect to the EBWR design.
Date: 1960
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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VARI Solution of Simultaneous, First-Order, Ordinary, Differential Equations

Description: VARI solves on the IBM-650 a system of simultaneous, first-order, ordinary, differential equations. The program was written so that a large number of calculations could be done in a reasonable length of time. The program permits the consideration of the production of the isotope by absorption and/or decay of one or more of any of the other isotopes in the chain.
Date: March 15, 1960
Creator: Kerr, B. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experimental Investigations of the Removal of Sodium Oxide From Liquid Sodium

Description: Experimental investigations were conducted to obtain additional information on the growth and characteristics of sodium oxide deposits in liquid sodium which could lead to system plugging. These investigations included the removal of sodium oxide from molten sodium by the cold trap method.
Date: January 18, 1960
Creator: Billuris, G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Powered Tanker Design and Economic Analysis - Direct Cycle Boiling Water Reactor

Description: A design and economic analysis is presented for a 44,000 DWT tanker utilizing a 27,300 shp direct cycle boiling water reactor propulsion system. Included are design descriptions and drawings, estimates of operating and capitol costs for the reference ship, estimates of long range potential, descriptions of required research and development programs, a preliminary safeguards analysis, an analysis of ship's motion on boiling water reactor performance, a summary reactor physics analysis, and a dis… more
Date: December 15, 1959
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Collected Methods for Analysis of Sodium Metal

Description: Methods for analyzing chemical impurities in sodium metal samples are presented. Chemical analysis was used to determine the following impurities: Calcium, Carbon, Chromium, Iron, Lithium, Nickel, Oxygen, Potassium, and Zirconium. Spectrographic analysis was used to determine many other impurities. Sodium samples obtained from experimental apparatus operated as part of the work being conducted for Atomics International were analyzed by these methods.
Date: October 15, 1959
Creator: Perrine, H. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Post-Irradiation Examination of Cored, Edge Loaded, Thoria-Urania Nuclear Fuel

Description: Three edge loaded thoria-urania nuclear fuel samples were assembled into a capsule, irradiated and examined. This irradiation was the first of a series to develop thoria-urania fuel for high heat flux, specific power and burn-up operation in a sodium graphite reactor.
Date: July 15, 1959
Creator: Slosek, T. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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N. S. Savannah Fuel Design and Development Program: Fuel Rod Vibration (Preliminary Report)

Description: This is a preliminary report on the investigation of the N.S. Savannah replacement fuel rod vibration amplitude when excited by water flowing parallel to the axis of the fuel rod. Methods of calculating the fuel rod frequency in air were verified by experiment. Work is continuing to establish the validity of methods of calculating natural frequencies in water and to confirm the correlation of flow induced vibration amplitude found in reference (1).
Date: September 25, 1959
Creator: Bailey, J. A. & Shields, C. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hydraulic Instability In a Natural Circulation Loop With Wet Steam Generation at 1000 PSIA

Description: Experimental test loops have been used to study the problem of hydraulic stability. The oscillatory behavior of a single-phase and two-phase natural circulation loop has been examined at atmospheric pressures and oscillating modes of operation were studied in terms of heat input.
Date: July 15, 1959
Creator: Levy, S. & Beckjord, E. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Rhode Island and Providence Plantations Atomic Energy Commission Nuclear Science Center Volume II - Safeguard Report

Description: This report presents the description and safeguard evaluation of an open pool research and test reactor rated at one megawatt. The reactor is being proposed by the General Electric Company to the Rhode Island and Providence Plantation Atomic Energy Commission.
Date: May 20, 1959
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Amendment No. 4 to Hazards Summary Report For The Dresden Nuclear Power Station

Description: This report is an amendment to the Preliminary Hazards Summary Report (1) and the Operating Procedures and Emergency Plans (5) for the Dresden Nuclear Power Station, submitted to the United States Atomic Energy Commission on September 3, 1957, and June 5, 1958, respectively.
Date: February 6, 1959
Creator: Commonwealth Edison Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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NPR; Tube to Nozzle Connection and Zircaloy-2 to Stainless Steel Tube Connection

Description: Zircaloy-2 tubing was successfully joined to austenetic and ferritic stainless steel tubing by fusion bonding. Tungsten inert gas welding was employed to join a flange to a pressure tube. This work was performed to help determine the design of pressure tubes of a pressure tube reactor.
Date: November 18, 1958
Creator: Smith, W. R. & Klepfer, H. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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