Fragility modeling of steel containments with localized corrosion

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 385, Issue , 1999, Pages 101-105

  Ellingwood, Bruce R ^a   Cherry, Jeffery L ^b   Naus, Dan J ^c  

^a Johns Hopkins University   (United States)

^b SANDIA NATIONAL LABORATORIES   (United States)

^c OAK RIDGE NATIONAL LABORATORY   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

CORROSION; MATHEMATICAL MODELS; REINFORCED CONCRETE; STEEL;

CONTAINMENTS;

NUCLEAR POWER PLANTS;

EID: 0033326128     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (12)

1. Cherry, J., 1997, "Analysis of containment structures with corrosion damage," Proc. 24th Water Reactor Safety Information Meeting, NUREG/CP-0157, US Nuclear Regulatory Commission, Washmgton,DC, pp. 333 - 352.
2. Clauss, D.B., Horschel, D.S. and Blejwas, T.E., 1987, "Insights into the behavior of LWR steel containment buildings during severe accidents," Nuclear Engrg. and Des., Vol. 100, pp. 189-204.
3. Ellingwood, B. and Hwang, H.H.M., 1985, Probabilistic descriptions of resistance of safety-related structures in nuclear plants," Nuclear Engrg. and Des. Vol. 88, pp. 169-178.
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6. Ellingwood, B., Bhattacharya, B. and Zheng, R.-H., 1996, "Reliability-based condition assessment of steel containments and liners," Report NUREG/CR-5442, US Nuclear Regulatory Commission, Washington, DC.
7. Ellingwood, B. and Cherry, J., 1999, "Fragility modeling of aging containment metallic pressure boundaries," Report to ORNL.
8. Hancock, J.W. and MacKenzie, A.C., 1976, "On the mechanisms of ductile failure in high-strength steels subjected to multi-axial stress states," J. Mech. Phys. Solids. Vol. 24. pp. 147-169.
9. "Individual plant examination program: perspectives on reactor safety and plant performance," 1996, Report NUREG-1560, Vois. 1 and 2. US Nuclear Regulatory Commission, Washington, DC.
10. Kennedy, R.P. and Ravindra, M.K., 1984, "Seismic fragilities for nuclear power plant studies," Nuclear Engrg. and Des., Vol. 79, pp. 47-68.
11. Naus, D.J., et al, 1997, "Aging of the containment pressure boundary in light-water reactor plants," Proc. 24th Water Reactor Safety Information Meeting, NUREG/CP-0157, U.S. Nuclear Regulatory Commission, pp. 309-332.
12. Pilch, M.M., Allen, M.D. and Klamerus, E.W., 1995, "Resolution of the direct containment heating issue for all Westinghouse plants with large dry containments or subatmospheric containments," Report NUREG/CR-6338, US Nuclear Regulatory Commission, Washington, DC.