Dynamic event tree analysis as a risk management tool

International Congress on Advances in Nuclear Power Plants 2010, ICAPP 2010

Volumn 2, Issue , 2010, Pages 979-986

  Metzroth, Kyle ^a   Denning, Richard ^a   Aldemir, Tunc ^a  

^a OHIO STATE UNIVERSITY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

AIRCRAFT CRASH; BRANCHING RULES; DYNAMIC EVENTS; EVENT TREE ANALYSIS; FUEL TEMPERATURE; HEAT REMOVAL; MITIGATION STRATEGY; REACTOR VESSEL; RECOVERY STRATEGIES; RECOVERY TIME; RESPONSE TIME; SEVERE ACCIDENT; SEVERE ACCIDENT MANAGEMENT; SODIUM FAST REACTORS; STOCHASTIC PROCESS; SYSTEM ANALYSIS; SYSTEM MODELS;

AIRCRAFT ACCIDENTS; DYNAMIC ANALYSIS; FAST REACTORS; NUCLEAR ENERGY; NUCLEAR POWER PLANTS; NUCLEAR REACTOR ACCIDENTS; RANDOM PROCESSES; RISK ANALYSIS; RISK MANAGEMENT; SODIUM; STOCHASTIC MODELS; TOWERS;

PROBABILITY DISTRIBUTIONS;

EID: 77956214110     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (14)

1. U. S. N. R. COMMISSION, "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants," U.S. Nuclear Regulatory Commission, Washington, D.C.NUREG-1150, 1990.
2. A. HAKOBYAN, T. ALDEMIR, R. DENNING, S. DUNAGAN, D. KUNSMAN, B. RUTT, U. CATALYUREK, "Dynamic Generation of Accident Progression Event Trees", Nuclear Engineering and Design, 238, 3457-3467 (2008).
3. T. SHUKRI. "Implementation of a Cognitive Human Reliability Model Dynamic Probabilistic Risk Assessment of a Nuclear Power Plant (ADS-IDA)" Ph.D. diss., University of Maryland, 1997
4. J. DEVOOGHT, C. SMIDTS "Probabilistic Reactor Dynamics I: The Theory of Continuous Event Trees", Nuclear Science and Engineering, 111, 229-240 (1992).
5. C. ACOSTA, N. SIU "Dynamic Event Trees in Accident Sequence Analysis: Application to Steam Generator Tube Rupture", Reliab. Engng & System Safety, 41, 135-154(1993).
6. G. COJAZZI, "The DYLAM Approach to the Dynamic Reliability Analysis of Systems", Reliab. Engng & System Safety, 52,279-296 (1996).
7. K. HSUEH, A. MOSLEH, "The development and application of the accident dynamic simulator for dynamic probabilistic risk assessment of nuclear power plants", Reliability Engineering System Safety, 52 (1996), 297-314
8. E. HOFER, et al., "An approximate epistemic uncertainty analysis approach in the presence of epistemic and aleatory uncertainties", Reliability Engineering and System Safety, 11 (2002), 229-238
9. K. METZROTH, R. DENNING, C. SMIDTS, T. ALDEMIR, "Incorporation of a Human Reliability Model into the ADAPT PRA Methodology", PSAM9: International Conference on Probabilistic Safety Assessment & Management, CD-ROM, International Association for Probabilistic Safety Assessment and Management, California (2008)
10. K. METZROTH, et al., "Linking of the RELAP5-3D Thermal-Hydraulic Code with the ADAPT PRA Tool", Proceedings of the Transactions of the American Nuclear Society", Vol. 100, p. 448, American Nuclear Society, Atlanta, United States (2009)
11. J.C. HELTON, F.C. Davis, "Latin hypercube sampling and the propagation of uncertainty in analyses of complex systems", Reliability Engineering and System Safety, 81 (2003), 23-69
12. The RELAP5-3D Code Development Team, RELAP5-3D Code Manual, Volume I: Code Structure, System Models, and Solution Methods, INEEL-EXT-98-00834, June 2005.
13. CE. BOARDMAN. "Optimizing the Size of the Super-Prism Reactor", Proceedings of ICONE 8, April 2000
14. R. WINNINGHAM et al., "Passive Heat Removal System Recovery Following an Aircraft Crash using Dynamic Event Tree Analysis," Trans, of the American Nuclear Society, Vol 100, p. 461, American Nuclear Society, Atlanta, United States, 2009