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ABWR: PL-2 Design Report

Description: From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date: October 15, 1960
Creator: Combustion Engineering, inc. Nuclear Division.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Analysis of Stresses in Bellows

Description: Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date: October 15, 1964
Creator: Anderson, W. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Boiling Studies for Sodium Reactor Safety: Part 2, Pool Boiling and Initial Force Convection Tests and Analyses

Description: Abstract: In fulfillment of the general objective of developing information on two-phase flow required in the safety evaluation of sodium cooled reactors, pool and forced-convection boiling of sodium were studied both experimentally and analytically.
Date: October 15, 1964
Creator: Lurie, H. & Noyes, R. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Carbide Fuel Development: Phase 1 Report, Period of May 15 to September 15, 1959

Description: From foreword: This report describes the work accomplished including the Conceptual Design task and the initial results of the tasks on Facility Design and Fabrication, Fuel Fabrication and Evaluation, and Fuel Reprocessing.
Date: October 15, 1959
Creator: Bolomey, R.; Lazerus, S.; Sapir, J.; Sofer, G.; Steinmetz, H.; Strasser, A. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Carbide Fuels in Fast Reactors

Description: Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Construction Completion Report: CAI-816, 100-N Reactor Plant

Description: Report from Hanford Laboratories concerning "the design and construction of the 100-N Reactor and heat dissipation plant complete with the necessary auxiliaries" (p. 2). Details of its construction and the plant's systems and instrumentation are described as well as economic considerations.
Date: October 15, 1964
Creator: Buckner, C. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Criticality-Accident Dosimetry Studies

Description: Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.
Date: October 15, 1964
Creator: Bailey, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design Modifications to the SRE during FY 1960

Description: Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date: February 15, 1961
Creator: Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Design Study: Sodium Modular Reactor

Description: This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date: January 15, 1960
Creator: General Electric Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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