displaying 81 - 90 results in total 1041
Ashmore, F. S.
view article (1.0)Assessment of the Risk.Fire Safety ConsultantsUniversity 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., 1987Ashmore, F. S.
view article (1.0)Selection of the System.Fire Safety ConsultantsUniversity 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., 1987U.S. Nuclear Regulatory Commission
view article (1.0)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
view article (1.0)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
view article (1.0)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
view article (1.0)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
view article (1.0)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
view article (1.0)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
view article (1.0)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
view article (1.0)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.