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Operating and Safety Problems in a Research Reactor

Description: Abstract. The purpose of this paper is to present, in the light of 20 years of reactor-operation experience at ORNL, what is being done in preparation for operation of the HFIR (High Flux Isotope Reactor). This paper considers only the areas of staffing and training; development of operating and maintenance procedures; preoperational testing of water systems; and testing of remote handling tools. The preparatory work in other areas such as the hydraulic tests, neutron tests, etc., is not cover… more
Date: October 23, 1963
Creator: McCord, R. V.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Study of the Transient Correction Factor Used in TREAT Reactor In-Pile Experiments

Description: The transient correction factor (TCF) is used in TREAT reactor experiments to predict the power calibration coefficient (PC) for prototype LMFBR fuel pins at transient conditions without subjecting the pins to a reactor transient. The TCF is defined as the fissions in a monitor wire per MW of reactor power at transient conditions divided by the fissions in a monitor wire per MW of reactor power at low power conditions. The power calibration factor is the power in the target fuel gram of Uranium… more
Date: 1978?
Creator: Graff, Dale L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Final Summary Safeguards Report For The General Electric Test Reactor

Description: This report is submitted to the U. S. Atomic Energy Commission as a final summary safeguards and hazards evaluation of a proposed test reactor at its Vallecitos Atomic Laboratory in Alameda County of California. It is the purpose of this report to provide sufficient data to obtain an AEC facility license for the reactor.
Date: February 20, 1958
Creator: Andersen, R. K. & Jacobs, I. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Hazards Summary Report: Babcock & Wilcox Test Reactor

Description: This preliminary Hazards Summary Report presents to the Atomic Energy Commission (AEC), Division of Licensing and Regulation, a description of the Nuclear Development Center, the characteristics of the proposed site, and an evaluation of the potential hazards associated with operating the test reactor at this location.
Date: July 1962
Creator: Babcock & Wilcox Company
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Reactor Progress Report

Description: Technical report describing the building of safety devices and features for the Oak Ridge reactor by the Reactor Safeguard Committee of the Atomic Energy Commission. Outlines the difficulties encountered in detailed design and construction operations for the facility.
Date: October 1, 1948
Creator: Brookhaven National Laboratory
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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EBR-II Dry Critical Experiments Experimental Program, Experimental Procedures, and Safety Considerations

Description: Report containing zero power (<1 kw) Dry Critical Experiments that were "to be conducted in the EBR-II Reactor prior to filling the Primary System with sodium coolant" (p. 7.) The two primary objectives of these experiments were to determine how well the system performed without sodium coolant and to "determine and/or verify certain operational data to permit modification or improvement of the system (neutron shield, instrumentation, etc.) prior to the introduction of sodium into the system" (p… more
Date: February 1961
Creator: Koch, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Conference on Waste Processing; Meeting of the U.S. Atomic Energy Commission Waste Processing Committee March 27-28, 1950; Section 1. Brookhaven National Laboratory Waste Problems

Description: Technical report summarizing the waste problems of the Brookhaven National Laboratory site and the integration of projects constituting the need for intensive and extended research into the development of processes, equipment, and systems to dispose of this nuclear waste. This report also outlines the first session for the March 27-28, 1950 meeting of the Committee at Brookhaven National Laboratory.
Date: 1950
Creator: Hayner, J. H. & Manowitz, B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design of the Movable and Fixed Control Components for the Consolidated Edison Thorium Reactor

Description: Prototype testing and thorough design analyses have proven the control components for the Consolidated Edison Thorium Reactor are adequate to withstand loads imposed during operation and handling. Assumptions made in the design analyses and cycles run during prototype testing subjected the components to more rigid conditions that are anticipated during actual operation. Results indicate the control components meet their design requirements.
Date: August 1960
Creator: Gestson, D. K.; Collings, D. M. & Maynard, W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Extended SM-2 Critical Experiments : CE-2

Description: Abstract: This technical report contains a description and results of a second series of critical experiments performed on the SM-2 core mock-up, as additional to the first series of experiments reported in APAE No. 54. The SM-2 core mock-up contains 36.4 kg U-235 and and estimated 67.9 gm B-10. The equivalent diameter and the active height are about 22 in.; the metal-to-water volume ration is 0.344. Data is presented on activation, reactivity, and stuck rod measurements. All measurements were … more
Date: June 30, 1961
Creator: McCool, W. J.; Robinson, R. A.; Weiss, S. H.; Raby, T. M.; Schrader, E. W. & Walthousen, L. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Burst Characteristics Associated with the Slow Assembly of Fissionable Materials

Description: This technical report is a sequel to LA-596, "Efficiency for Very Slow Assembly" by K. Fuchs. Herein are given estimates of temperature rise and pressure developed as a result of active material slowly being driven supercritical. Marginal assembly rates can thus be determined for both metal and solution assemblies above which the disassembly by thermal expansion is explosive in the sense that the active material or containing vessel is ruptured.
Date: July 1952
Creator: Hansen, G. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Some Control Rod Applications and Operating Experience in Power Reactor Environments

Description: Information obtained in a survey of control rod applications and operating experience is reported. This survey covered the Army Nuclear Power Program, the Organic Moderated Reactor Experiment, the Yankee Atomic Power Plant, the Shippingport Pressurized Water Reactor and the Argonne Experimental Boiling Water Reactor.
Date: December 14, 1960
Creator: Williamson, H.E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Plutonium Discharge Rates and Spent Nuclear Fuel Inventory Estimates for Nuclear Reactors Worldwide

Description: This report presents a preliminary survey and analysis of the five primary types of commercial nuclear power reactors currently in use around the world. Plutonium mass discharge rates from the reactors’ spent fuel at reload are estimated based on a simple methodology that is able to use limited reactor burnup and operational characteristics collected from a variety of public domain sources. Selected commercial reactor operating and nuclear core characteristics are also given for each reactor ty… more
Date: September 1, 2012
Creator: Castle, Brian K.; Hoiland, Shauna A.; Rankin, Richard A. & Sterbentz, James W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Experiments and Analysis for SM-1 Core II With Special Components

Description: Abstract: This technical report contains a summary of analytical and experimental work performed on SM-1 Core II, with special components is presented. The effects of these special assemblies upon power distribution and core reactivity were calculated and compared to experimental measurements. A thermal analysis was conducted to determine steady state and transient performance of the special test components of the core as well as some of the hotter standard Core II components. Experimental work… more
Date: January 1, 1961
Creator: Lee, D. H.; Robinson, R. A. & Segalman, I.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW

Description: Hazard report on the Experimental Boiling Water Reactor that covers the basic modifications to the plant as designed to increase the present operating design rating of 20 Mw(t) to a new rating of 100 Mw(t). Changes and additions to the plant, core, reactor vessel, and other major components are shown. An analysis of the effects of the changes on the performance and safety of the reactor is presented.
Date: December 1959
Creator: Wimunc, E. A. & Harrer, J. M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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