FireDOC Search

displaying 81 - 90 results in total 1041

  • Ashmore, F. S.
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    Assessment of the Risk.
    Fire Safety Consultants
    University of Edinburgh. Recent Developments in Fire Detection and Suppression Systems. (With Additional Papers From a Course of the Same Title--July 8-9, 1987). November 10-12, 1986, Edinburgh, Scotland, 8 p., 1987

  • Ashmore, F. S.
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    Selection of the System.
    Fire Safety Consultants
    University of Edinburgh. Recent Developments in Fire Detection and Suppression Systems. (With Additional Papers From a Course of the Same Title--July 8-9, 1987). November 10-12, 1986, Edinburgh, Scotland, 13 p., 1987

  • U.S. Nuclear Regulatory Commission
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    Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix 9. Safety Design Rationale for Nuclear Power Plants.
    Nuclear Regulatory Commission, Washington, DC
    ['WASH-1400', 'NUREG 75-014']
    WASH-1400; NUREG 75-014
    October 1975
    42 p.

  • U.S. Nuclear Regulatory Commission
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    Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix 10. Design Adequacy.
    Nuclear Regulatory Commission, Washington, DC
    ['WASH-1400', 'NUREG 75-014']
    WASH-1400; NUREG 75-014
    October 1975
    146 p.

  • U.S. Nuclear Regulatory Commission
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    Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix 6. Calculation of Reactor Accident Consequences.
    Nuclear Regulatory Commission, Washington, DC
    ['WASH-1400', 'NUREG 75-014']
    WASH-1400; NUREG 75-014
    October 1975
    524 p.

  • U.S. Nuclear Regulatory Commission
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    Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix 5. Quantitative Results of Accidents Sequences.
    Nuclear Regulatory Commission, Washington, DC
    ['WASH-1400', 'NUREG 75-014']
    WASH-1400; NUREG 75-014
    October 1975
    123 p.

  • U.S. Nuclear Regulatory Commission
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    Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix 3. Failure Data.
    Nuclear Regulatory Commission, Washington, DC
    ['WASH-1400', 'NUREG 75-014']
    WASH-1400; NUREG 75-014
    October 1975
    97 p.

  • U.S. Nuclear Regulatory Commission
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    Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix 4. Common Mode Failures. Bonding Techniques and Special Techniques.
    Nuclear Regulatory Commission, Washington, DC
    ['WASH-1400', 'NUREG 75-014']
    WASH-1400; NUREG 75-014
    October 1975
    48 p.

  • U.S. Nuclear Regulatory Commission
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    Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix 2. Fault Trees.
    Nuclear Regulatory Commission, Washington, DC
    ['WASH-1400', 'NUREG 75-014']
    WASH-1400; NUREG 75-014
    October 1975
    604 p.

  • U.S. Nuclear Regulatory Commission
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    Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants. Appendix 1. Accident Definition and Use of Event Trees.
    Nuclear Regulatory Commission, Washington, DC
    ['WASH-1400', 'NUREG 75-014']
    WASH-1400; NUREG 75-014
    October 1975
    110 p.