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PILOT PLANT SHUTDOWN AND Pu-Al PROCESSING

Description: The large aqueous pilot plant facilities at ORNL were cleaned and are being put in standby condition. Experience was gained during the year as anion exchange was used to recover more than one kg of plutonium left in the exploded evaporator system. This experience is being applied to a new recovery program just beginning in cell 1 of Building 4507. (auth)
Date: September 25, 1961
Creator: Bresee, J.C.
Partner: UNT Libraries Government Documents Department
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Configuration Management Program Plan

Description: Westinghouse Savannah River Company (WSRC) has established a configuration management (CM) plan to execute the SRS CM Policy and the requirements of the DOE Order 4700.1. The Reactor Restart Division (RRD) has developed its CM Plan under the SRS CM Program and is implementing it via the RRD CM Program Plan and the Integrated Action Plan. The purpose of the RRD CM program is to improve those processes which are essential to the safe and efficient operation of SRS production reactors. This document provides details of this plan.
Date: September 25, 1991
Partner: UNT Libraries Government Documents Department
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Hallam Nuclear Power Facility, Preoperational Test Interim Report Dry Excess Loading

Description: A test to obtain data for use in determining the reactivlty wohh of Na in the Hallam reactor core is described. The test is designed to obtain information on the dry temperature coefficient of reactivity and to train operators. An evaluation of results is included. (J.R.D.)
Date: February 25, 1962
Creator: Kempt, H.C. & Corcoran, W.P.
Partner: UNT Libraries Government Documents Department
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Preliminary design data package. Appendices C1 and C3. [HYBRID 2; VSYS; and CRASH]

Description: The computer programs, including HYBRID, VSYS, VEHIC and CRASH, used to compute the energy and fuel consumption, life-cycle costs and performance characteristics of a hybrid electric-powered vehicle are described and their use documented. (LCL)
Date: July 25, 1979
Partner: UNT Libraries Government Documents Department
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Theoretical study of the structure, energetics, and dynamics of silicon and carbon systems using tight-binding approaches

Description: Semiempirical interatomic potentials are developed for silicon and carbon by modeling the total energy of the system using tight-binding approaches. The parameters of the models were obtained by fitting to results from accurate first-principles Local Density Functional calculations. Applications to the computation of phonons as a function of volume for diamond-structured silicon and carbon and the thermal expansions for silicon and diamond yields results which agree well with experiment. The physical origin of the negative thermal expansion observed in silicon is explained. A tight-binding total energy model is generated capable of describing carbon systems with a variety of atomic coordinations and topologies. The model reproduces the total energy versus volume curves of various carbon polytypes as well as phonons and elastic constants of diamond and graphite. The model has also been used in the molecular-dynamics simulation of the properties of carbon clusters. The calculated ground-state geometries of small clusters (C{sub 2}--C{sub 10}) correlates well with results from accurate quantum chemical calculations, and the structural trend of clusters from C{sub 2} to C{sub 60} are investigated. 67 refs., 19 figs.
Date: October 25, 1991
Creator: Xu, Chunhui.
Partner: UNT Libraries Government Documents Department
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EXPERIMENTAL MEASUREMENTS OF THE SUCTION HEAD REQUIRED BY THE HALLAM PROTOTYPE FREE SURFACE SODIUM PUMP

Description: Hydraulic tests were made on the Hallam Prototype Free-Surface Sodium Pump to determine the net positive suction head (NPSH) required at various sodium flow rates. Pump performance data were also collected. The results indicate that an NPSH of 22 ft sodium is required at the design flow rate of 7200 gpm at approximates 1000 deg F, agreeing with computed values, and that the pump is designed with a safety margin of slightly over l0%. (D.L.C.)
Date: July 25, 1961
Creator: Atz, R.W.
Partner: UNT Libraries Government Documents Department
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GRAPHITE-STAINLESS STEEL COMPATIBILITY STUDIES

Description: S>The compatibility of type 304L stainless steel in intimate contact with graphite is being studied as a function of temperature and contact pressure. This study is an outgrowth of materials compatibility problems in present and advanced gas-cooled reactors, where structural members in direct contact with graphite provide the possibility of both carburization and self-welding. Initial studies were concerned with surface reactions in the absence of gaseous contaminants under a vacuum of 10/sup -6/ mm Hg at 540 to 705 deg C. Stainless steel specimens are pretreated to provide three surface conditions: H/sub 2/- fired, preoxidized, and Cu-plated. Surface contact pressures ranged from 0 to 10,000 psi. Test results are presented which establish the lower temperature limit for significant diffusion between graphite and stainless steel at approximately 60O deg C. Above this temperature, diffusion between untreated or H2-fired stainless steel surfaces was found to effect complete bonding of the two materials at contact pressures as low as 500 psi. Bonding was effectively prevented by the presence of either an oxide film or a Cu plate at temperatures up to 700 deg C. Where bonding occurred, diffusion rates measured for C in stainless steel were comparable with those reported for stainless steel ln C- saturated Na. However, phases produced in surface reactions between graphite and stainless steel were of higher order than those reported for the Na carrier. Lack of carburization in control specimens not in contact with graphite indicated the role of the gas phase to be unimportant at impurity pressures of 10/sup -6/ mm Hg. (auth)
Date: September 25, 1962
Creator: Fleischer, B.; DeVan, J. H. & Coobs, J. H.
Partner: UNT Libraries Government Documents Department
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Pakistan: A Bibliography

Description: This report is a bibliography that cites information related to Pakistan. It includes General, History, Government and Politics, Economy and Development, Foreign policy, and defense.
Date: November 25, 1969
Creator: Patitucci, Jean B.
Partner: UNT Libraries Government Documents Department
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Do-It-Yourself Ecology

Description: This report deals with how to develop a good environment.
Date: May 25, 1970
Creator: Environmental Action Inc.
Partner: UNT Libraries Government Documents Department
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Major Natural Disasters in the United States: 1959-1969

Description: This report provides a listing of major natural disasters in the United States between 1959 and 1969. It lists the name of the event, the estimated costs of damage, and fatality numbers for each disaster.
Date: February 25, 1970
Creator: Keyser, C. Frank
Partner: UNT Libraries Government Documents Department
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Kilowatt Isotope Power System: component test report for the Ground Demonstration System Alternator Stator

Description: Results are presented of acceptance tests conducted on the Alternator Stator, S/N 002, for the Kilowatt Isotope Power System. These results show that the Alternator Stator, S/N 002 for the Kilowatt Isotope Power System has satisfactorily completed the testing set forth within Sundstrand Test Specification 2538. Test requirements of TS 2538 were extracted from the Kilowatt Isotope Power System, and Phase I Test Plan.
Date: April 25, 1978
Creator: Brainard, E.L.
Partner: UNT Libraries Government Documents Department
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Advanced Gas Cooled Nuclear Reactor Materials Evaluation and Development Program. Progress report, January 1, 1980-March 31, 1980

Description: Results are presented of work performed on the Advanced Gas-Cooled Nuclear Reactor Materials Evaluation and Development Program. The objectives of this program are to evaluate candidate alloys for Very High Temperature Reactor (VHTR) Nuclear Process Heat (NPH) and Direct Cycle Helium Turbine (DCHT) applications, in terms of the effect of simulated reactor primary coolant (helium containing small amounts of various other gases), high temperatures, and long time exposures, on the mechanical properties and structural and surface stability of selected candidate alloys. A second objective is to select and recommend materials for future test facilities and more extensive qualification programs. Included are the activities associated with the status of the simulated reactor helium supply system, testing equipment and gas chemistry analysis instrumentation and equipment. The progress in the screening test program is described, including screening creep results and metallographic analysis for materials thermally exposed or tested at 750, 850, and 950/sup 0/C.
Date: June 25, 1980
Partner: UNT Libraries Government Documents Department
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Monthly energy review, October 1991. [Contains glossary]

Description: This report presents current data on production, consumption, stocks, imports, exports, and prices of the principal energy commodities in the United States. Also included are data on international production of crude oil, consumption of petroleum products, petroleum stocks, and production of electricity from nuclear-powered facilities. 36 figs., 57 tabs.
Date: October 25, 1991
Partner: UNT Libraries Government Documents Department
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Assessment of the potential of colloidal fuels in future energy usage. Final report. [97 references]

Description: Pulverized coal has been an increasing important source of energy over the past century. Most large utility boilers, all modern coking plants, and many industrial boilers and blast furnaces employ pulverized coal as a major feed stream. In periods of oil shortages, such as during World Wars I and II, the concept of adding powdered coal to oil for use in combustion equipment originally designed for oil has been actively pursued but rarely used. Over this same period of time, there have been attempts to use air suspensions of coal dust in diesel engines in Germany, and in turbines in various countries. The economic advantages to be enjoyed by substitution of powdered coal in oil are not generally realized. Oil costs at $30/bbl represent a fuel value of about $5.00/10/sup 6/ Btu; coal at $25/ton is equivalent to approximately $1.00/10/sup 6/ Btu. Although capital costs for the use of coal are higher than those associated with the use of oil, coal is clearly becoming the least costly fuel. Not only are considerable cost advantages possible, but an improvement in balance of payments and an increase in reliability of fuel supplies are other potential benefits. It is therefore recommended that increased national attention be given to develop these finer grinds of carbonaceous fuels to be used in various suspending fluids. Technical areas where significant additional support appear desirable are described.
Date: February 25, 1980
Partner: UNT Libraries Government Documents Department
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Preliminary design data package. Appendix C

Description: The design requirements, design philosophy, method and assumptions, and preliminary computer-aided design of the Near-Term Hybrid Vehicle including its electric and heat power units, control equipment, transmission system, body, and overall vehicle characteristics are presented. (LCL)
Date: July 25, 1979
Partner: UNT Libraries Government Documents Department
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Fire protection countermeasures for containment ventilation systems

Description: The goal of this project is to find countermeasures to protect High Efficiency Particulate Air (HEPA) filters, in exit ventilation ducts, from the heat and smoke generated by fire. Initially, methods were developed to cool fire-heated air by fine water spray upstream of the filters. It was recognized that smoke aerosol exposure to HEPA filters could also cause disruption of the containment system. Through testing and analysis, several methods to partially mitigate the smoke exposure to the HEPA filters were identified. A continuous, movable, high-efficiency prefilter using modified commercial equipment was designed. The technique is capable of protecting HEPA filters over the total time duration of the test fires. The reason for success involved the modification of the prefiltration media. Commercially available filter media has particle sorption efficiency that is inversely proportional to media strength. To achieve properties of both efficiency and strength, rolling filter media were laminated with the desired properties. The approach was Edisonian, but truncation in short order to a combination of prefilters was effective. The application of this technique was qualified, since it is of use only to protect HEPA filters from fire-generated smoke aerosols. It is not believed that this technique is cost effective in the total spectrum of containment systems, especially if standard fire protection systems are available in the space. But in areas of high-fire risk, where the potential fuel load is large and ignition sources are plentiful, the complication of a rolling prefilter in exit ventilation ducts to protect HEPA filters from smoke aerosols is definitely justified.
Date: August 25, 1980
Creator: Alvares, N.; Beason, D.; Bergman, V.; Creighton, J.; Ford, H. & Lipska, A.
Partner: UNT Libraries Government Documents Department
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Summary of HRT Run 25

Description: Run 25 was the final period of power operational of the HRT. The reactor was operated for periods of 62, 8, 52, and 80 hours at 5 Mw with no outward indication of fuel and core and blanket average temperatures of 270 and 230 deg C, respectively. The uranium concentration in the was 1.7 to 2.0 g U/kg D/sub 2/O. Longer periods of operation were prevented by mechanical difficulties, notably with the fuel feed pump. While the reactor was subcritical after the last of the above runs, the upper patch in the core tank wall became dislodged, allowing greater core-to-blanket mixing. The resultant blanket uranium concentration was 2.9 g U/kg D/sub 2/O. The reactor was subsequently operated at April 28, 1961. The experiment was operated at high temperature for a total of 10,866 hours. The system was critical for a total of 8,841 hours and produced 16,295 Mwhours of power. The fuel, heavy water, and some corrosion specimens were recovered, and the reactor was stored in an assembled state. (auth)
Date: July 25, 1962
Creator: Engel, J. R.; Bauman, H. F.; Buchanan, J. R.; Haubenreich, P. N.; Piper, H. B. & Richardson, D. M.
Partner: UNT Libraries Government Documents Department
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Development of a Fluidized Bed Calcination Process for Aluminum Nitrate Wastes in a Two-Foot-Square Plant Calciner. Part 2. Factors Affecting the Intra-Particle Porosity of Alumina

Description: A seven- to twenty-fold volume reduction can be obtained from fluidized bed calcination of aqueous aluminum nitrate wastes, depending on the operating conditions employed and their effect on the intra-panticle porosity and absolute density of the calcined alumina. Among the calcining variables, only the bed temperature and the fuel aluminum concentration had a significant effect on the intra-particle porosity of alumina generated during studies conducted primarily in a two-foot-square fluidized bed calciner. A quantitative correlation of the effect of these variables is presented. Alumina with an intra-particle porosity as low as five per cent can be generated by employing a suitable combination of low bed temperature and dilute aluminum feed concentration. Feed sodium concentration and product alpha alumina content were found to have minor effect on intra-particle porosity. Results also show that an inverse relationship exists between the nitrate content of the calcine and the calcination temperature. (auth)
Date: July 25, 1962
Creator: Wheeler, B. R.; Grimmett, E. S. & Buckham, J. A.
Partner: UNT Libraries Government Documents Department
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Spectrographic Determination of Impurities in Hafnium

Description: A spectrographic method using d-c arc excitation in a controlled atmosphere was developed to analyze for seven impurity elements in radioactive hafnium samples. Analysis requires as little as 35 mg of hafnium oxide. (auth)
Date: August 25, 1961
Creator: Ginther, B. E. & Wheeler, G. V.
Partner: UNT Libraries Government Documents Department
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Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre

Description: An addition is presented for the IBM-7090 program MURGATROYD to produce a rough graph of reactor power versus time. A sample of output is included for the case given as an example. (J.R.D.)
Date: May 25, 1962
Creator: Nestor, C. W. Jr.
Partner: UNT Libraries Government Documents Department
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