FireDOC Search

displaying 1 - 10 results in total 142

  • Dollezhal, N. A.
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    Graphite-Water Steam-Generating Reactor in the USSR.
    Academy of Sciences, Moscow, USSR
    Nuclear Energy, Vol. 20, No. 5, 385-390, October 1981

  • Graham, D. J.
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    Nuclear Firefighting Approach With Caution.
    Fire Protection Analyst, Phoenix, AZ
    Fire Chief, Vol. 31, No. 1, 42-44, January 1987

  • Goldstein, S.; Magnaud, J. P.
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    Turbulent Natural Convection in an Enclosure.
    Centre d'Etudes Nucleaires de Saclay, Gif-sur-Yvette, France
    ['CONF-830805--88', 'CEA-CONF-6984', 'DE84-750669']
    CONF-830805--88; CEA-CONF-6984; DE84-750669
    Structural Mechanics in Reactor Technology Conference. August 22-26, 1983, Chicago, IL, 1-14 p., 1983

  • DiNenno, P. J.; Dungan, K. W.
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    Effectiveness of Fire-Detection Systems in Light-Water-Reactor Facilities.
    Professional Loss Control, Inc., Oak Ridge, TN 37830
    ['DE81-029465', 'ALO-141']
    Sandia National Labs., Albuquerque, NM; Department of Energy, Washington, DC, DE81-029465; ALO-141
    August 1981
    100 p.

  • Bender, D. M.; Dunn, T. D.; Houghton, W. J.
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    Safety-Risk Assessment of the HTGR steam-Cycleicogeneration Plant.
    GA Technologies, Inc., San Diego, CA
    ['DE83-014929', 'GA-A-17000']
    Department of Energy, San Francisco, CA, DE83-014929; GA-A-17000
    May 1983
    110 p.

  • Hulme, B. L.
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    Boolean Methods of Optimization Over Independence Systems.
    Sandia National Lab., Albuquerque, NM
    ['SAND83-1304C', 'CONF-830647-1', 'DE83-013671']
    Department of Energy, Washington, DC, SAND83-1304C; CONF-830647-1; DE83-013671
    1983
    14 p.

  • Stehling, S. G.; Hunsicker, J. C.
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    Investigations into the Sodium-Steam Surface Interaction on a Stagnant Pool.
    General Electric Co., Sunnyvale, CA
    AM03-76SF00893
    AM03-76SF00893
    1977
    53 p.
    ASME-IEEE Joint Power Generation Conference. September 18-21, 1977, Los Angeles, CA, 1977

  • Kelly, M. J.; Parker, G. W.; Rochelle, J. M.
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    Development of the Capacitor Discharge Vaporization Technique to Produce Aerosols Formed Under Conditions Postulated for Hypothetical Core Disruptive Accidents.
    Oak Ridge National Lab., TN
    ['NUREG/CR-0226', 'ORNL/NUREG/TM-160', 'NRC FIN 80121']
    Nuclear Regulatory Commission, Wahsington, DC, NUREG/CR-0226; ORNL/NUREG/TM-160; NRC FIN 80121
    July 1978
    92 p.

  • Liu, D. D. S.; Harrison, W. C.; Tamm, H.; MacFarlane, R.; Clegge, L. J.
    view article (1.0)

    Canadian Hydrogen-Combustion Studies Related to Nuclear-Reactor-Safety Assessment.
    Atomic Energy of Canada Research Co., Manitoba, Canada
    AECL-6994
    AECL-6994
    1980
    37 p.
    Combustion Institute/Western StatesSection. Fall Meeting, 1980. October 20-21, 1980., Los Angeles, CA, 1980

  • Chan, M. K. W.; Mishima, J.
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    Characteristics of Combustion Products: A Review of the Literature.
    Pacific Northwest Lab., Richland, WA
    PNL-4174
    Nuclear Regulatory Comm., Washington, DC, PNL-4174
    July 1983
    165 p.