FireDOC Search

displaying 1 - 10 results in total 11

  • Foster, K. W.; Boassc, C. J.; Kaushal, N. N.
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    Clinch River Breeder Reactor Sodium Fire Protection System Design and Development.
    Rockwell International Corp., Canoga Park, CA
    ['CONF-8404418', 'DE84-008919']
    CONF-8404418; DE84-008919
    April 13, 1984
    7 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

  • Gerosa, A.
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    Italian Position Paper on the Safety Analysis of Liquid Metal Fast Breeder Reactors as Related to Sodium Fires. PEC Reactor.
    ENEA, Rome, Italy
    International Atomic Energy Agency. Sodium Fires, Design and Testing Specialists Meeting. Summary Report. May 24-28, 1982., Richland, WA, 35-42 p., 1982

  • Mitsutsuka, N.; Yoshida, N.
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    Japanese Studies on Sodium Fires, Design and Testing.
    Power Reactor and Nuclear Fuel Development Corp., Tokyo, Japan
    International Atomic Energy Agency. Sodium Fires, Design and Testing Specialists Meeting. Summary Report. May 24-28, 1982., Richland, WA, 43-48 p., 1982

  • 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.

  • Billings, M. P.; Swenson, L. D.
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    Leak-Rate Qualification of the FFTF Control Area.
    Hanford Engineering Development Lab., Richland, WA
    HEDL-SA-2829
    HEDL-SA-2829
    June 1983
    20 p.
    Health Physics Society. June 19-23, 1983., Baltimore, MD, 1983

  • Fields, D. E.; Cooper, A. C.; Miller, C. W.
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    Transport of Breeder Reactor-Fire-Generated Sodium Oxide Aerosols for Building-Wake-Dominated Meteorology.
    Tennessee Univ., Knoxville
    ORNL-6232
    Department of Energy, Oak Ridge, TN, ORNL-6232
    February 1987
    50 p.

  • Clauser, M. J.; Sciacca, F. W.; Senglaub, M. E.; Murata, K. K.
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    CONTAIN: A Code for Analysis of Breeder-Reactor Containment Response to Hypothetical Severe Accidents.
    Sandia National Labs., Albuquerque, NM
    SAND-82-0131C
    SAND-82-0131C
    1982
    10 p.

  • Copus, E. R.
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    Quantified Fault Tree Models for the Clinch River Breeder Reactor Engineered Safety Systems.
    Sandia National Labs., Albuquerque, NM
    ['NUREG/CR-1923', 'SAND81-0260', 'NRC Fin A1197']
    Nuclear Regulatory Commission, Washington, DC, NUREG/CR-1923; SAND81-0260; NRC Fin A1197
    May 1981
    30 p.

  • Zhang, X. L.; Vantelon, J. P.; Charpenel, J.; Malet, J. C.
    view article (1.0)

    Study of the Radiative Exchanges During a Sodium Jet Fire Developed in a Large Scale Cylindrical Enclosure.
    Poitiers Univ., France; CEN Cadarache, Cedex, France
    Fire Safety Journal, Vol. 15, No. 6, 451-469, 1989