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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 covered in this presentation.
Date: October 23, 1963
Creator: McCord, R. V.
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-235 per MW reactor power. The purpose of this study was to reduce the uncertainties concerning the transient correction factor by examining the nature and applicability of the TCF method.
Date: 1978?
Creator: Graff, Dale L.
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: The Babcock & Wilcox Company
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
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. 7.)
Date: February 1961
Creator: Koch, L. J.; Loewenstein, W. B.; Lovoff, A.; Hooker, H. H.; Monson, H. O.; Ramp, R. L. et al.
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

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.
Partner: UNT Libraries Government Documents Department
open access

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 conducted on the open seven control rod array employing 38 stationary fuel elements. Activation measurements consisted of neutron flux measurements using uranium fission foils for relative power distribution studies, the effect of flux suppressors on reducing power peaks, blocked coolant channel measurements, and gamma ray dose distribution. Reactivity measurements were performed to determine the effect f flow divider, flux suppressors and stimulated high temperature and pressure operation; b-10 loading in the SM-2 core; and core material coefficients. For the later, the worth in cents per gm or cents per cc was determined at simulated temperature of 510 degree F for B-10, U-235, stainless steel, and void. Stuck rod measurements were made to obtain an indication of the criticality margin in the event one or more control rods should stick in the operating position.
Date: June 30, 1961
Creator: McCool, W. J.; Robinson, R. A.; Weiss, S. H.; Raby, T. M.; Schrader, E. W. & Walthousen, L. D.
Partner: UNT Libraries Government Documents Department
open access

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 type. In addition to the worldwide commercial reactors survey, a materials test reactor survey was conducted to identify reactors of this type with a significant core power rating. Over 100 material or research reactors with a core power rating >1 MW fall into this category. Fuel characteristics and spent fuel inventories for these material test reactors are also provided herein.
Date: September 1, 2012
Creator: Castle, Brian K.; Hoiland, Shauna A.; Rankin, Richard A. & Sterbentz, James W.
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.
Partner: UNT Libraries Government Documents Department
open access

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 discussed includes individual reactivity effects of all the special elements and the total effect of all of the elements. Power mappings were also made and are reported.
Date: January 1, 1961
Creator: Lee, D. H.; Robinson, R. A. & Segalman, I.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Coolant Impurity Removal Equipment at the OMRE

Description: Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date: October 15, 1964
Creator: Barbour, P. & Davis, W. W.
Partner: UNT Libraries Government Documents Department
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