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ORR OPERATIONS FOR PERIOD APRIL 1958 TO APRIL 1959

Description: It has been the custom to report the operating experience at the ORR along with other activities in the reports of the ORNL Operations Division. It was decided to combine the sections of the Operations Division reports appropriate to ORR operation covering the year from April 1958 through March 1959. (W.D.M)
Date: September 10, 1959
Creator: Cox, J.A.
Partner: UNT Libraries Government Documents Department

SAFETY AND OPERABILITY REVIEW OF EXPERIMENTS TO BE OPERATED IN NUCLEAR REACTORS AT ORNL

Description: The operation of the tests and experiments conducted in the ORR, the LITR, and the ORNL Graphite Reactor is discussed. In order to minimize the possibility of any hazardous conditions developing into an incident involving the safety of personnel, the reactor, and other equipment, any experiment design and installation should be checked or reviewed to ensure that all conceivable dangers are recognized and that appropriate safeguards have been incorporated into the design. (W.D.M.)
Date: December 1, 1958
Creator: Cagle, C.D.
Partner: UNT Libraries Government Documents Department

SHUT-DOWN COOLING OF ORR

Description: Information is presented that may be used in estimating the magnitude of the shutdown cooling problem in the ORR at various power levels. The information used in the investigation was obtained from other research reactors. (W.L.H.)
Date: August 14, 1959
Creator: Cole, T.E.
Partner: UNT Libraries Government Documents Department

ADMINISTRATION OF ORNL RESEARCH REACTORS

Description: Organization of the ORNL Operations division for administration of the Oak Ridge Research Reactor, the Low Intensity Testing Reactor, and the Oak Ridge Graphite Reactor is described. (J.R.D.)
Date: August 20, 1962
Creator: Casto, W. R.
Partner: UNT Libraries Government Documents Department

Oak Ridge Reservation Annual Site Environmental Report for 2006

Description: This document is prepared annually to summarize environmental activities, primarily environmental-monitoring activities, on the Oak Ridge Reservation (ORR) and within the ORR surroundings. The document fulfills the requirement of Department of Energy (DOE) Order 23l.IA, 'Environment, Safety and Health Reporting,' for an annual summary of environmental data to characterize environmental performance. The environmental-monitoring criteria are described in DOE Order 450.1, 'Environmental Protection Program.' The results summarized in this report are based on data collected prior to and through 2006. This report is not intended to provide the results of all sampling on the ORR. Additional data collected for other site and regulatory purposes, such as environmental restoration remedial investigation reports, waste management characterization sampling data, and environmental permit compliance data, are presented in other documents that have been prepared in accordance with applicable DOE guidance and/or laws and are referenced herein as appropriate. Corrections to the report for the previous year are found in Appendix A. Environmental monitoring on the ORR consists primarily of two major activities: effluent monitoring and environmental surveillance. Effluent monitoring involves the collection and analysis of samples or measurements of liquid and gaseous effluents at the point of release to the environment; these measurements allow the quantification and official reporting of contaminants, assessment of radiation and chemical exposures to the public, and demonstration of compliance with applicable standards and permit requirements. Environmental surveillance consists of the collection and analysis of environmental samples from the site and its environs; these activities provide direct measurement of contaminant concentrations in air, water, groundwater, soil, foods, biota, and other media. Environmental surveillance data provide information regarding conformity with applicable DOE orders and, combined with data from effluent monitoring, allow the determination of chemical and radiation dose/exposure assess ments of ORR operations and effects, if any, on the local environment.
Date: September 1, 2007
Creator: ORNL,Y-12,ETTP
Partner: UNT Libraries Government Documents Department

ALUMINUM DETERMINATION IN REACTOR COOLING WATER

Description: ABS>A method for determination of submicrogram quantities of Al in reactor cooling water by neutron activation analysis is described. Data obtained in analyses of samples from the OKR and the Bulk Shielding Reactor are included. (J.R.0.)
Date: September 1, 1958
Creator: Emery, J.F. & Leddicotte, G.W.
Partner: UNT Libraries Government Documents Department

ANALOG COMPUTER STUDY OF THE OPERATION OF THE GAS-COOLED LOOP ON THE OAK RIDGE RESEARCH REACTOR

Description: An annlog computer study of the ORR gas-cooled loop was made. The effects on fuel and gas temperatures of changing gas (nitrogen) flow rates, turning the heater on and off, and inserting or removing the fuel were determined. It was found that the temperature of the sample, if fuel, could be raised more rapidly than it could be reduced, and that the temperature could be reduced faster with high rates of flow. All of the equations used in building up the computer are given, and some of them are derived. (auth)
Date: July 1, 1958
Creator: Green, F.P.; Neill, F.H.; Short, B.E. & Winton, M.L.
Partner: UNT Libraries Government Documents Department

Studies of Improvement of Power Density in Orr Loops

Description: Using a simplified model, calculations were made of the possible effects of voids upon the power density in ORR loop experiments. It is concluded that the power density may be markedly increased if voids and channels are plugged with moderator material such as graphite or beryllium. (auth)
Date: April 11, 1960
Creator: Tobias, M. L. & Vondy, D. R.
Partner: UNT Libraries Government Documents Department

Interfacial Electrochemistry of Copper and Spectro-Electrochemical Characterization of Oxygen Reduction Reaction

Description: The first part of this dissertation highlights the contents of the electrochemical characterization of Cu and its electroplating on Ru-based substrates. The growth of Ru native oxide does diminish the efficiency of Cu plating on Ru surface. However, the electrochemical formed irreversible Ru hydrate dioxide (RuOxHy) shows better coverage of Cu UPD. The conductive Ru oxides are directly plateable liner materials as potential diffusion barriers for the IC fabrication. The part II of this dissertation demonstrates the development of a new rapid corrosion screening methodology for effective characterization Cu bimetallic corrosion in CMP and post-CMP environments. The corrosion inhibitors and antioxidants were studied in this dissertation. In part III, a new SEC methodology was developed to study the ORR catalysts. This novel SEC cell can offer cheap, rapid optical screening results, which helps the efficient development of a better ORR catalyst. Also, the SEC method is capable for identifying the poisoning of electrocatalysts. Our data show that the RuOxHy processes several outstanding properties of ORR such as high tolerance of sulfation, high kinetic current limitation and low percentage of hydrogen peroxide.
Date: August 2011
Creator: Yu, Kyle Kai-Hung
Partner: UNT Libraries

THE OAK RIDGE RESEARCH REACTOR (ORR), THE LOW-INTENSITY TESTING REACTOR (LITR), AND THE OAK RIDGE GRAPHITE REACTOR (OGR) AS EXPERIMENT FACILITIES

Description: >Characteristics of the ORR, LITR, and OGR that experimenters have found to be important are listed. The results of a survey conducted among experimenters on the utility of the reactors for various types of experiments are discussed, and some changes which might be made to improve the utilization are listed. A brief outline, with references, of most of the experiments currently being performed is included. (auth)
Date: August 28, 1962
Creator: George, K.D.
Partner: UNT Libraries Government Documents Department

AN INVESTIGATION OF THE STRUCTURAL INTEGRITY OF SELECTED COMPONENTS OF THE OAK RIDGE RESEARCH REACTOR

Description: An investigation was made to determine the structural behavior of selected components of the Oak Ridge Research Reactor for increased power level conditions. It was found that a reactor cooling water outlet temperature of 150 deg F will cause severe plastic strain cycling in the aluminum housings for the large test facilities. Increasing the reactor cooling water flow rate of 21,000 gpm will cause plastic deformations in certain reaons of the core box. These latter deformations can be tolerated, but the full implications asscciated with any change in pressure differential must be understood before adopting the above flow rate. (auth)
Date: July 22, 1960
Creator: Corum, J M; Greenstreet, B L; Maxwell, R L & Rosenthal, M W
Partner: UNT Libraries Government Documents Department