FireDOC Search

displaying 91 - 100 results in total 142

  • U.S. Nuclear Regulatory Commission
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    NRC Safety Research in Support of Regulation, 1987.
    Nuclear Regulatory Comm., Washington, DC
    NUREG-1266, Vol. 2, May 1988, 56 p.

  • Brown, R. V.; Ulvila, J. W.
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    Does a Reactor Need a Safety Backfit? Case Study on Communicating Decision and Risk Analysis Information to Managers.
    Decision Science Consortium, Inc., Reston, VA
    Risk Analysis, Vol. 8, No. 2, 271-282, June 1988

  • French Republic, Ministry of Research and Industry
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    Basic Safety Rules. Part 5: General Rules Applicable to Several Systems, Structures or Components. Chapter 2: Other General Rules.
    SIN-E-6230-82, December 1982, 10 p.

  • Gray, B. F.; Felton, P. G.
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    Low-Temperature Oxidation in a Stirred-Flow Reactor. Part 1. Propane.
    Leeds Univ., England
    Combustion and Flame, Vol. 23, 295-304, 1974

  • Baxter, J. T.
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    N Reactor External Events Probabilistic Risk Assessment.
    Westinghouse Hanford Co., Richland, WA
    WHC-SA-0753, October 1989, 10 p.
    U.S. Department of Energy. Natural Phenomena Hazards Mitigation Conference, 2nd. October 3-5, 1989, Knoxville, TN, 1989

  • Lee, S. P.
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    CANDU 3 Incorporates New Concepts.
    CANDU Operations, Mississauga, Canada
    Nuclear Engineering International, Vol. 35, No. 429, 31-32, April 1990

  • Majumdar, K. C.; Alesso, H. P.; Altenbach, T. J.
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    On Fire Risk/Methodology for the Next Generation of Reactors and Nuclear Facilities.
    Lawrence Livermore National Laboratory, CA
    Department of Energy, Washington, DC, UCRL-JC-110420, October 15, 1992, 7 p.
    American Nuclear Society Meeting. January 27-29, 1993, Clearwater, FL, ['1992', '1993']

  • Buzzard, R. J.; Sheffler, K. D.
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    Effect of Long-Time, Elevated-Temperature Exposures to Vacuum and Lithium on the Properties of a Tantalum alloy, T-111.
    NASA Lewis Research Center, Cleveland, OH
    National Aeronautics and Space Administration, Washington, DC, NASA TN D-7548, March 1974, 33 p.

  • U.S. Nuclear Regulatory Commission
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    NRC Safety Research in Support of Regulation, FY 1993.
    Nuclear Regulatory Commission, Washington, DC
    NUREG-1266, Vol. 8, June 1994, 89 p.

  • Vanttola, T.; Puska, E. K.
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    RETU: The Finnish Research Program on Reactor Safety. Interim Report. 1995-May 1997.
    VTT-Technical Research Center of Finland, Espoo
    VTT Research Notes 1856, 1997, 219 p.