[1] | American Institute of Chemical Engineers, Layer of Protection Analysis - Simplified process risk assessment, New York, USA, October 2001 | ||
[2] | ANDREWS, J.D., DUNNETT, S.J. Event Tree Analysis using Binary Decision Diagrams, IEEE Trans. Reliability, Vol 49, pp 230-238, 2000 | ||
[3] | ASME Standard for Probabilistic Risk Assessment for Nuclear Power Plant Applications, ASME RA-S-2002, 2002, Amended by addenda ASME RA-Sa-2003, ASME RA-Sb2005, and ASME RA-Sc-2007 | ||
[4] | BRABAND, J., LENNARTZ, K. A Systematic Process for the Definition of Safety Targets for Railway Signalling Applications, Signal+Draht, 9/99 | ||
[5] | DOWELL, III, A.M., HENDERSHOT, D.C. Simplified Risk Analysis - Layer of Protection Analysis (LOPA), American Institute of Chemical Engineers, Indianapolis, 2002 | ||
[6] | Expert Group on Probabilistic Safety Analysis for Nuclear Power Plants: "Methods for Probabilistic Safety Analysis for Nuclear Power Plants, Status: August 2005", BfS-SCHR-37/05, Salzgitter, October 2005 (In German) | ||
[7] | FULLWOOD, R.; HALL, R. Probabilistic Risk Assessment in the Nuclear Power Industry, NewYork, 1988 | ||
[8] | GOLDBERG, B.E., EVERHART, K│ STEVENS, R., BABBITT III, N., CLEMENS,P│ STOUT, L. System Engineering "Toolbox" for Design-Oriented Engineers, NASA Reference Publication 1358,1994 | ||
[9] | Guidelines on Modeling Common Cause Failures in Probabilistic Risk Assessment, NUREG/CR-5485, NRC 1998 | ||
[10] | HENLEY, E.J., KUMAMOTO, H. Reliability Engineering and Risk Assessment, 1981 | ||
[11] | HOFER, E., KLOOS, M., KRZYKACZ-HAUSMANN, B., PESCHKE, J., SONNENKALB, M. Dynamic Event Trees for Probabilistic Safety Analysis, Gesellschaft Anlagen-und Reaktorsicherheit (GRS), Proceedings EUROSAFE, Berlin 4-5 November 2002 | ||
[12] | ISO/IEC 31010 Risk management - Risk assessment guidelines | ||
[13] | IEC 60300-3-1:2003 | Dependability Management - Part 3-1: Application guide-Analysis techniques for dependability - Guide on methodology | |
[14] | IEC 60300-3-9:1995 | Dependability management-Part 3: Application guide - Section 9: Risk analysis of technological systems | |
[15] | IEC 60812:2006 | Analysis techniques for system reliability - Procedure for failure mode and effects analysis (FMEA) | |
[16] | IEC 61078:2006 Analysis techniques for dependability - Reliability block diagram and boolean methods | ||
[17] | IEC 61165:2006 Application of Markov techniques | ||
[18] | IEC 61508 (all parts) Functional safety of electrical/electronic/programmable electronic safety-related systems | ||
[19] | IEC 61511-3:2003 | Functional safety - Safety instrumented systems for the process industry sector - Part 3: Guidance for the determination of the required safety integrity levels | |
[20] | IEC 61703:2001 | Mathematical expressions for reliability, availability, maintainability and maintenance support terms | |
[21] | IEC 62425:2007 | Railway applications - Communication, signalling and processing systems - Safety related electronic systems for signaling | |
[22] | IEC 62429:2007 Reliability growth - Stress testing for early failures in unique complex systems | ||
[23] | IEC 62508:2010 Guidance on human aspects of dependability | ||
[24] | IEC 62551 Analysis techniques for dependability- Petri net techniques | ||
[25] | ISO 3534-1:2006 Statistics - Vocabulary and symbols - Part 1: General statistical terms and terms used in probability | ||
[26] | KLOOS, M., PESCHKE, J., MCDET: A Probabilistic Dynamics Method Combining Monte Carlo Simulation with the Discrete Dynamic Event Tree Approach, Nuclear Science and Engineering: 153,137-156, 2006 | ||
[27] | LEVESON, N.G. SAFEWARE: System Safety and Computers, Addison-Wesley Publishing Company, 1995 | ||
[28] | McCORMICK, N.J. Reliability and Risk Analysis - Methods and Nuclear Power Applications, Boston, 1981 | ||
[29] | Nuclear Regulatory Commission, PRA Procedures Guide, A Guide to the Performance of Probabilistic Risk Assessments for Nuclear Power Plants, Final Report, NUREG/CR-2300 Vol. 1, January 1983 | ||
[30] | NIELSEN, D.S. The Cause/Consequence Diagram Method as a Basis for Quantitative Accident Analysis, Danish Atomic Energy Commission, RISO-M-1374, May 1971 | ||
[31] | Nuclear Regulatory Commission, Reactor Safety Study: An Assessment of Accident Risks in US Commercial Nuclear Power Plants, Rep. WASH-1400-MR(NUREG-75/014), Washington, DC, 1975 | ||
[32] | PAPAZOGLOU, I. A. Mathematical foundations of event trees, Reliability Engineering and System Safety 61 (2008) 169-183, Northern Island, 2008 | ||
[33] | Railtrack, Engineering Safety Management System, Issue 2.0, "Yellow Book", 1997 | ||
[34] | RAUSAND, M., HOYLAND, A. System Reliability Theory - Models, Statistical Methods and Applications, Hoboken, New Jersey, 2004 | ||
[35] | SIU, N. Risk Assessment for Dynamic Systems: An Overview, Reliability Engineering and System Safety 43,1994, p. 43-73 | ||
[36] | SMITH, D.J. Reliability, Maintainability and Risk, Oxford, 2001 | ||
[37] | Special subject: Common cause failure analysis, Kerntechnik Vol 71, No 1-2, Carl Hanser-Verlag, February 2006, pp 8-62 | ||
[38] | VILLEMEUR, A. Reliability, Availability, Maintainability and Safety Assessment. Volume 1. Methods and Techniques, Chichester, Wiley, 1992 | ||
[39] | XU, H.; DUGAN, J.B. Combining Dynamic Fault Trees and Event Trees for Probabilistic Risk Assessment, University of Virginia, January 2004 | ||
[40] | ZIO, E. An Introduction to the Basics of Reliability and Risk Analysis, Series in Quality, Reliability and Engineering Statistics, Vol. 13, 2007 |
УДК 62-192:658.562:006.354 | ОКС 21.020 | Т59 |
Ключевые слова: событие, вероятность события, частота события, успех события, отказ события, дерево событий, узел, инициирующее событие, последовательность событий, главное событие, ветвь |
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М.: Стандартинформ, 2015