Treatment of uncertainties in modeling the failure of major RCS components in severe accident analysis

Transactions of the American Nuclear Society

Volumn 94, Issue , 2006, Pages 177-179

  Hakobyan, Aram ^a   Denning, Richard ^a   Aldemir, Tune ^a   Dunagan, Sean ^b   Kunsman, David ^b  

^a OHIO STATE UNIVERSITY   (United States)

^b SANDIA NATIONAL LABORATORIES   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

EID: 33746065252     PISSN: 0003018X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (4)

1. M. HASSAN, T. ALDEMIR, "A Data Base Oriented Dynamic Methodology for the Failure Analysis of Closed Loop Control Systems in Process Plants", Reliab.Engng & System Safety, 27, 275-322 (February 1990).
2. R. M. SUMMERS, R. K. COLE, E. A. BOUCHERON, M. K. KARMEL, S. E. DINGMAN, J. E. KELLY, "MELCOR 1.8.0: A Computer Code for Nuclear Reactor Severe Accident Source Term and Risk Assessment Analyses", Nuclear Regulatory Commission, Washington, DC (1991)
3. Y. LIAO, K. VIEROW, "MELCOR Analysis of Steam Generator Tube Creep Rupture in Station Blackout Severe Accident", Nuclear Technology, pp. 302-313 (2005)
4. S. MAJUMDAR, "Prediction of Structural Integrity of Steam Generator Tubes Under Severe Accident Conditions", Nuclear Engineering and Design, pp. 31-55 (1999)