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, 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, 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
    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, 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
    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, 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
    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.
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    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