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TECHNICAL PUBLICATIONS OF BATTELLE-NORTHWEST DURING 1970

Description: This report is one of an annual series and announces formal research and development reports and technical articles published during 1970 by Battelle-NorthwesL The reports and articles are grouped by broad subject categories and arranged alphabetically by author within each category, except Progress Reports, which are arranged chronologically, An author index and report number index are also included"
Date: March 1, 1971
Creator: Smith, E. F.
Partner: UNT Libraries Government Documents Department

THERMOPHORETIC VELOCITY OF LARGE AEROSOL PARTICLES

Description: The velocity of thermal repulsion of large aerosol particles has been calculated by others by equating the thermal force on a stationary partlcle to the Stokes-Cunningham viscous force. This procedure is theoretically unsound because the boundary conditions employed in the viscous force equation are erroneous when the particle moves in a thermal gradient. In the current study these difficulties have been circumvented by rederiving the thermal force equation, allowing for a relative velocity between the particle and the gas stream. The velocity of motion is then calculated by setting the net force on the particle equal to zero. The velocity obtained by this more realistic approach agrees with that calculated by the former method, which is surprising in view of the incorrect boundary conditions employed in the former method. Investigation of the drag force equation shows that the thermal force and the viscous force are exerted independently of each other, which explains this unexpected agreement, The range of applicability of the analysis is explored by comparison with available experimental data,
Date: November 1, 1965
Creator: Postma, A. K.
Partner: UNT Libraries Government Documents Department

A TOTAL BURN SPECTROGRAPHIC DETERMINATION OF SILICON IN PLUTONIUM

Description: A total burn-spectrographic method has been applied to the determination of trace concentrations of silicon in plutonium. The sample is oxidized to plutonium dioxide, mixed with a germanium dioxide-graphite mixture containing tin internal standard, packed into cupped graphite electrodes, and burned to completion in a high amperage direct current arc. Plutonium spectral interference is minimized by optical means and by use of a less intense silicon line. The sensitivity is thereby decreased but is still sufficient to determine 25 ppm of silicon in plutonium. The precision of the method is estimated to be �8% (relative standard deviation) at the 270 ppm level and �14% at 40 ppm.
Date: July 1, 1965
Creator: Ko, Roy
Partner: UNT Libraries Government Documents Department

REACTOR PHYSICS QUARTERLY REPORT JANUARY, FEBRUARY, MARCH 1970

Description: The objective of the Reactor Physics Quarterly Report is to inform the scientific community in a timely manner of the technical progress made on the many phases of reactor physics work within the laboratory. The report contains brief technical discussions of accomplishments in all areas where significant progress has been made during the quarter.
Date: May 1, 1970
Creator: Schmid, L. C.; Clayton, E. D. & Heineman, R. E.
Partner: UNT Libraries Government Documents Department

STATISTICAL ANALYSIS AND MODELING OF GAP CONDUCTANCE DATA FOR REACTOR FUEL RODS CONTAINING UO2 PELLETS

Description: The purpose of this study was threefold: To examine a large body of in-reactor data for UO{sub 2} pellet fuel where internal temperatures have been measured, and to estimate fuel surface temperature, cladding inner temperature, and thus gap conductance under a consistent set of assumptions. To estimate the variance (due to experimental uncertainties) in the inferred gap conductance values. To attempt a correlation of the gap conductance values with design parameters and operating conditions (e.g., with cold diametral gap and local linear power).
Date: May 1, 1974
Creator: Lanning, D. D.; Hann, C. R. & Gilbert, E. S.
Partner: UNT Libraries Government Documents Department

REVIEW OF REACTOR SAFETY ANALYSES OF FAST AND LIQUID METAL COOLED REACTORS

Description: Safety analysis reports on United States fast and liquid metal cooled reactors were reviewed to gain a better understanding of the safety philosophy applied to the design of these facilities. This information was compiled to help guide the design and safety analysis of the Fast Flux Test Facility. No attempt was made to draw conclusions concerning the relative merit of different approaches and philosophies used by different reactor design teams. The facilities reviewed were; Enrico Fermi Atomic Power Plant (FERMI) Hallam Nuclear Power Facility (HALLAM) Southwest Experimental Fast Oxide Reactor (SEFOR) Fast Reactor Test Facility (FARET) Experimental Breeder Reactor No. 1 (EBR-I) Experimental Breeder Reactor No. 2 (EBR-II) Fast Reactor Zero Power Experiment (ZPR - III). The information gathered from the safety analysis reports is tabulated under these headings: Control and Safety Systems; Reactor Protection Systems; Backup Systems; Containment or Confinement Systems; Inherent Reactivity Effects and Important Physics Parameters; Fuel and Fuel Handling; Accidents Considered and Chemical Problems; Site; Exhaust Ventilation System; and Waste Effluents.
Date: November 1, 1967
Creator: Shaver, R. E. & Wittenbrock, N. G.
Partner: UNT Libraries Government Documents Department

STATUS OF DATA RETRIEVAL SYSTEM AS OF APRIL 1, 1969

Description: Battelle-Northwest is developing a general-purpose data retrieval system. The system is planned to provide almost unrestricted flexibility in application and use, with no limitations on the quantity of data, except those imposed by hardware. This data retrieval system is being programmed in Fortran-V, for batch processing on a Univac-1108. The control, search-and-retrieval, query-input, output, and startup programs have been written in preliminary form, and are in the initial debugging and test stages. Current versions of these programs are presented.
Date: June 1, 1969
Creator: Reynolds, R. L.; Engel, R. L.; Toyooka, R. T. & Wells, E. L.
Partner: UNT Libraries Government Documents Department

QUARTERLY PROGRESS REPORT JANUARY, FEBRUARY, MARCH, 1967 REACTOR FUELS AND MATERIALS DEVELOPMENT PROGRAMS FOR FUELS AND MATERIALS BRANCH OF USAEC DEVISION OF REACTOR DEVELOPMENT AND TECHNOLOGY

Description: Work is reported in the areas of: fast fuels oxides and nitrides; nuclear ceramics; nuclear graphite; basic swelling studies; irradiation damage to reactor metals; ATR gas loop operation and maintenance; metallic fuels; nondestructive testing research; and fast reactor dosimetry and damage analysis.
Date: June 1, 1967
Creator: Albaugh, F. W.; Bush, S. H.; Cadwell, J. J.; de Halas, D. R. & Worlton, D. C.
Partner: UNT Libraries Government Documents Department

Pacific Northwest Laboratory Monthly Activities Report, Division of Biology and Medicine Programs: June 1967

Description: Work is reported in these areas: general radiation effects; toxicity of radioelements; studies at the molecular and cellular levels; environmental radiation studies; atmospheric radioactivity and fallout; marine sciences; radiological and health physics; and radiation instruments.
Date: July 1, 1967
Partner: UNT Libraries Government Documents Department

Pacific Northwest Laboratory Monthly Activities Report, Division of Production and Materials Management and Hanford Plant Assistance Programs: March 1974

Description: Tasks are reported that were done in assistance to the Atlantic Richfield Hanford Company in the area of process technology and development, and in assistance to the Hanford Plant in the areas of environmental evaluations, radiation protection, and radiation standards and engineering.
Date: April 1, 1974
Creator: Alpen, E. L.
Partner: UNT Libraries Government Documents Department

PARAMETRIC REACTIVITY TRANSIENT ANALYSES FOR THE FFTF NUCLEAR PROOF TEST REACTOR

Description: Fault tree techniques have been used to identify possible failure paths within the NPTR which could lead to core disassembly. The analysis o f the various faults has led to formulation of design requirements, protective system requirements, and administrative restraints required to prevent accidents from these faults. Transient analyses were performed using the heat transfer-nuclear kinetics codes, Nutiger-II, FORE-II, and MELT-II . To verify results, intercomparison studies were made between the codes. The codes were i n good general agreement. Each code was found to exhibit different advantages and disadvantage. Inherent reactivity feedback effects were assessed in the analysis. With the assumed core parameters, there appears to be sufficient Doppler to prolong a nuclear transient to allow protective action to prevent fuel from melting. The use of average values of the feedback coefficients smeared over the entire core does not appear to be an acceptable method with spacially dependent temperatures. In the thermal analysis, the fuel pin gap coefficient and sodium film coefficient do not appear to be highly sensitive parameters for transient analysis. Power transients resulting from reactivity insertions of from 2$/sec to 20$/sec have been examined in detail. Sodium will be molten before fuel melting occurs for accidents within this range. For the smaller ramp rates (< 4$/sec), sodium nay even reach vaporization temperatures before any fuel melts. Power transients terminated by effective protective action were investigated. It i s believed p o s s i b l e t o design a scram system, with the . present state of the art, to prevent sodium from melting for a reactivity ramp up to at least 6$/sec. This same system would prevent fuel melting for a reactivity ramp up to 15$/sec. Sodium thermal expansion will play a very important role in a core disassembly. When the average sodium ...
Date: January 1, 1970
Creator: Schade, A. R.
Partner: UNT Libraries Government Documents Department

PERMANENT MAGNET AND PITOT-STATIC PROBE FLOMETERS FOR LIQUID SODIUM

Description: A permanent magnet probe flowmeter and a Pitot-static bubbler flowmeter are considered for coolant flow measurement in the Fast Test Reactor. The permanent magnet probe offers a sensitivity on the order of tenths of a millivolt per foot/second flow velocity, appropriate linearity of response, simplicity of operation, and no contact between liquid metal and electrical insulation. Its applicability is contingent on magnetic material having sufficient magnetization retention in high temperature and high neutron flux environments. The Pitot-static bubbler offers low sensitivity to nuclear radiation, use of off-the-shelf materials, and high, though non-linear, sensitivity. Positive displacement flow in the bubbler may eliminate plugging of the probe tubing by sodium oxide.
Date: May 1, 1969
Creator: Lessor, D. L. & Duane, B. H.
Partner: UNT Libraries Government Documents Department

PHYSICAL EFFECTS OF THE HANFORD WINDSTORMS OF JANUARY 11, 1972 AND JANUARY 21, 1972

Description: The windstorm of January 11 caused a minor amount of damage to the Hanford Reservation and Hanford vicinity. Damage sustained to Hanford Reservation structures (roofing, flashing, fences, windows) was approximately $20,000. One building did receive structural damage to roof members. Evidence that wind pressures did not reach 30 lb/ft{sup 2} during the January 11 windstorm was provided in the fact that specially designed exterior wall panels did not fail. These panels were designed and carefully proof-tested to insure that they would fail at a loading of 30 lb/ft{sup 2} as a requirement of structural safety in the original design-construction program in 1952-1954. There was one power outage on the Hanford Reservation due to the January 11 windstorm (Rattlesnake Mountain Observatory). Damage to power lines and electrical facilities amounted to about $1600. Damage to structures in the Hanford vicinity (excluding the Hanford Reservation) from the January 11 windstorm was estimated to cost $13,000. This does not include damage to private residences, etc., which has been estimated by others to be near $250,000. Power line damage in the Hanford vicinity amounted to about $80,000, of which $60,000 was accounted for in the loss of four transmission towers in the tie-line between Priest Rapids and Wanapum Dams. The January 21 windstorm, which struck Toppenish, Washington, was a straight-wind of the catabatic foehn type and not a tornado-type wind as described in newspaper accounts. No funnel cloud was associated with this windstorm. The maximum gust was about 85 mph at 30 ft above the ground. Cost estimates of damage in Toppenish were not available. There were no power outages or structural damage on the Hanford Reservation from the January 21 windstorm. Total damage to the Hanford Reservation from the two windstorms was estimated to be about $22,500.
Date: June 1, 1972
Creator: Henager, C. H. & Fuquay, J. J.
Partner: UNT Libraries Government Documents Department

POSTIRRADIATION EXAMINATION OF CENTRIFUGALLY BONDED EBR-11 DRIVER FUEL

Description: BNW was requested by AEC/DRDT to assist ANL with the postirradiation examination of EBR-II driver fuel (U + 5Fs) pins that became shortened during irradiation. To date, three irradiated pins and one nonirradiated pin were examined.
Date: July 31, 1969
Creator: Leggett, R. D.; Hann, D. R.; Last, G. A. & Gruber, W. J.
Partner: UNT Libraries Government Documents Department

Reactor Flow and Pressure Drop Study

Description: A study was made to determine the flow rates and pressure drops for all primary system flow paths through the FTR. The main data and results are in tables, diagrams and curves. The results are intended to provide a common basis for evaluation of parametric changes in the system.
Date: July 15, 1969
Creator: Keyes, R. E.
Partner: UNT Libraries Government Documents Department

BOUND PERIODICAL HOLDINGS BATTELLE - NORTHWEST LIBRARY

Description: This report lists the bound periodicals in the Technical Library at the Pacific Northwest Laboratory, operated by Battelle Memorial Institute. It was prepared from a computer program and is arranged in two parts. Part one is an alphabetical list of journals by title; part two is an arrangement of the journals by subject. The list headings are self-explanatory, with the exception of the title code, which is necessary in the machine processing. The listing is complete through June, 1966 and updates an earlier publication issued in March, 1965.
Date: May 1, 1967
Partner: UNT Libraries Government Documents Department