Reliability-based service life assessment of concrete structures in nuclear power plants: Optimum inspection and repair

Nuclear Engineering and Design

Volumn 175, Issue 3, 1997, Pages 247-258

  Ellingwood, Bruce R ^a   Mori, Yasuhiro ^b  

^a JOHNS HOPKINS UNIVERSITY   (United States)

^b NAGOYA UNIVERSITY   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

CONCRETE CONSTRUCTION; EVALUATION; INSPECTION; OPTIMIZATION; RELIABILITY; REPAIR; SERVICE LIFE;

IN SERVICE INSPECTION;

NUCLEAR POWER PLANTS;

EID: 0031549876     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(97)00042-3     Document Type: Article

References (24)

1. ACI, 1990. Code requirements for nuclear safety related concrete structures (ACI 349-85(90)), American Concrete Institution, Detroit, MI.
2. ASME, 1992. Reliability-based inspection-development of guidelines'. Report NUREG/GR-0005 (prepared by the American Society of Mechanical Engineers), US Nuclear Regulatory Commission, Washington, DC.
3. Clifton, J.R., Knab, L.I., 1989. Service life of concrete. NUREG/CR-5466 (prepared by the National Bureau of Standards), US Nuclear Regulatory Commission, Washington, DC.
4. Ellingwood, B., 1992. Probabilistic risk assessment. In: Blockley, D. (Ed.), Engineering Safety, McGraw-Hill, London, pp. 89-116.
5. Ellingtood, B., Mori, Y., 1993. Probabilistic methods for condition assessment and life prediction of concrete structures in nuclear plants. Nucl. Eng. Des. 142, 155-166.
6. Hookham, C.J., 1991. Structural aging assessment methodology for concrete structures in nuclear power plants, ORNL/NRC/LTR-90/17 (prepared by Multiple Dynamics). Oak Ridge National Laborary, Oak Ridge, TN.
7. Hwang, H., Ellingwood, B., Shinozuka, M., Reich, M., 1987. Probability based design criteria for nuclear plant structures. ASCE J. Struct. Eng. 113 (5), 925-942.
8. Krauss, P.D., 1994. Repair materials and techniques for concrete structures in nuclear power plants, ORNL/NRC/ LTR-93/28 (prepared by Wiss, Janney, Elstner and Associates). Oak Ridge National Laboratory, Oak Ridge, TN.
9. Madsen, H., Sorensen, J.D., Olesen, R., 1989. Optimal inspection planning for fatigue damage of offshore structures. In: Structural Safety and Reliability, Proc. ICOSSAR 1989, Vol. III, American Society of Civil Engineers, New York, pp. 2099-2106.
10. Mori, Y., Ellingwood, B., 1993. Methodology for reliability-based condition assessment - application to concrete structures in nuclear plants. Report NUREG/CR-6052, US Nuclear Regulatory Commission, Washington, DC.
11. Mori, Y., Ellingwood, B., 1994a. Maintaining reliability of concrete structures I: role of inspection-repair. ASCE J. Struct. Eng. 120 (3), 824-845.
12. Mori, Y., Ellingwood, B., 1994b. Maintaining reliability of concrete structures II: optimum inspection-repair. ASCE J. Struct. Eng. 120 (3), 846-862.
13. Naus, D.J., et al., 1993. An overview of the ORNL/NRC program to address aging of concrete structures in nuclear power plants. Nucl. Eng. Des. 142, 329-339.
14. Naus, D.J., Oland, C.B., Ellingwood, B., 1996. Report on aging of nuclear power plant reinforced concrete structures, NUREG/CR-6424. US Nuclear Regulatory Commission, Washington, DC.
15. Rahman, S., Grigoriu, M., 1993. Markov model for seismic reliability analysis of degrading structures. ASCE J. Struct. Eng. 119 (6), 1844-1865.
16. Regulatory Guide, 1990. Inservice inspection of ungrouted tendons in prestressed concrete containments, 1.35, US Nuclear Regulatory Commission, Washington, DC.
17. Shah, V.N., Hookham, C.J., 1994. Aging management of light water reactor concrete containments, in: Proc. 21st Water Reactor Safety Information Meeting, NUREG/CP-0133, Vol. 3, US Nuclear Regulatory Commission, Washington, DC, pp. 283-306.
18. Snyder, K.A., Clifton, J.R., Carino, N.J., 1992. Nondestructive evaluation of the in-place compressive strength of concrete based upon limited destructive testing, NISTIR 4874. National Institute of Standards and Technology, Gaithersburg, MD.
19. Tao, Z., Corotis, R.B., Ellis, J.H., 1995. Reliability-based structural design with Markov decision processes. ASCE J. Struct. Eng. 121 (6), 971-980.
20. Veneziano, D., Grigoriu, M., Cornell, C.A., 1977. Vector process models for system reliability. ASCE J. Eng. Mech. 103 (3), 441-460.
21. Vesely, W.E., 1987. Risk evaluations of aging phenomena: the linear aging reliability model and its extensions, in: Proc. 14th Water Reactor Safety Information Meeting, NUREG/CP-0082(3), pp. 335-350.
22. Vesikari, E., 1988. Service life of concrete structures with regard to corrosion of reinforcement, Research Report, Technical Research Center for Finland, Espoo.
23. Vora, J.P. et al., 1991. Nuclear plant aging research (NPAR) program plan, Report NUREG-1144. US Nuclear Regulatory Commission, Washington, DC.
24. Yang, J., 1994. Application of reliability methods to fatigue, quality assurance and maintenance, in: A.A. Balkema (ed.), Structural Safety and Reliability, Proc. ICOSSAR 1993, Vol. I, Rotterdam, The Netherlands, pp. 3-18.