displaying 31 - 40 results in total 492
Murphy, G. A.; Casada, M. L.; Johnson, M. P.; Muhlheim, M. D.; Rooney, J. J.
view article (1.0)Survey and Evaluation of System Interaction Events and Sources. Appendices C and D. Volume 2. Technical Report.Nuclear Operations Analysis Center, Oak Ridge, TN; JBF Assocates, Inc., Knoxville, TNNuclear Regulatory Commission, Washington, DC, ORNL/NOAC-244 Vol.2.; NUREG/CR-3922-V2, January 1985, 264 p.Murphy, G. A.; Casada, M. L.; Johnson, M. P.; Muhleim, M. D.; Rooney, J. J.
view article (1.0)Survey and Evaluation of System Interaction Events and Sources. Appendices A and B. Volume 1. Technical Report.Nuclear Operation Analysis Center, Oak Ridge, TN; JBF Associates, Inc., Knoxville, TNNuclear Regulatory Commission, Washington, DC, NUREG/CR-3922; ORNL/NOAC-224 Vol.1., January 1985, 114 p.Azarm, M. A.; Bari, R. A.; Boccio, J. L.; Hanan, N.; Papazoglou, I. A.
view article (1.0)Review of the Limerick Generating Station Severe Accident Risk Assessment. Review of Core-Melt Frequency.Brookhaven National Lab., Upton, NYNuclear Regulatory Commission, Washington, DC, NUREG/CR-3493; BNL-NUREG-51711, July 1984, 194 p.Alvares, N. J.
view article (1.0)Assessment of Extent and Degree of Thermal Damage to Polymeric Materials in the Three Mile Island Unit 2 Reactor Building. Volume 6.Lawrence Livermore National Lab., Livermore, CAEG and G Idaho, Inc.; Department of Energy, Three Mile Island, PA, GEND-INF--023-Vol. 6; DE84-010031, February 1984, 59 p.International Association for Fire Safety Science. Fire Safety Science. Proceedings. 1st International Symposium October 7-11, 1985, Hemisphere Publishing Corp., New York, Gaithersburg, MD, Grant, C. E.; Pagni, P. J., Editors, 647-656 p., 1986Solomon, K. A.; Nelson, P. F.; Chiesa, J. R.; Wolf, K.
view article (1.0)Evaluation of Alternative Safety Criteria for Nuclear Power Plants.Rand Corporation, Santa Monica, CARisk Analysis, Vol. 4, No. 3, 209-216, September 1985Kazarians, M.; Siu, N. O.; Apostolakis, G.
view article (1.0)Fire Risk Analysis for Nuclear Power Plants: Methodological Developments and Applications.Lowe and Garrick, Inc., Newport Beach, CA; California Univ., Los AngelesRisk Analysis, Vol. 5, No. 1, 33-51, March 1985Bastien, M. C.; Duman, M.; Laporte, J.; Parmentier, N.
view article (1.0)Evacuation Risks: A Tentative Approach for Quantification.Commissariat a l'Energie Atomique, Roses, FranceRisk Analysis, Vol. 5, No. 1, 53-61, March 1985Schneider, U.
view article (1.0)Fire Protection Reglations in Nuclear Power Plants Based on Building Code Requirements. (Regelung des Brandschutzes in Kernkraftwerken auf der Grundlage Bauaufsichtlicher Vorschriften.)Bauingenieurwesen Universtitat-Gesamthochschule Kassel, West GermanyMarch 1984, 150 p.Chanin, D. I.; Shiver, A. W.; Bennett, D. E.
view article (1.0)Toxic Gas Accident Analysis Code User's Manual. Technical Report.Sandia National Lab., Albuquerque, NMNuclear Regulatory Commission, Washington, DC, NUREG/CR-3685; SAND84-0367, August 1984, 60 p.Lieber, K.
view article (1.0)Assessment of the Risk of a Plutonium Laboratory in Case of an Internal Fire.Swiss Federal Inst., Wurenlingen, SwitzerlandInternational Fire Protection Engineering Institute, 4th Proceeding. February 26-March 10, 1984, Brunnen, Switzerland, 1-12 p., 1984