Summary and conclusions of a program addressing aging of nuclear power plant concrete structures

Nuclear Engineering and Design

Volumn 194, Issue 1, 1999, Pages 73-96

  Naus, D J ^a   Oland, C B ^a   Ellingwood, B R ^b   Hookham, C J ^c   Graves Iii, H L ^d  

^a OAK RIDGE NATIONAL LABORATORY   (United States)

^b JOHNS HOPKINS UNIVERSITY   (United States)

^c 2902 Eisenhower ^*  (United States)

^d U S NUCLEAR REGULATORY COMMISSION   (United States)

Author keywords

[No Author keywords available]

Indexed keywords

ACCIDENT PREVENTION; AGING OF MATERIALS; CONCRETE CONSTRUCTION; ENVIRONMENTAL IMPACT; NUCLEAR MATERIALS SAFEGUARDS; RELIABILITY; STRUCTURAL ANALYSIS;

AGING MANAGEMENT;

NUCLEAR POWER PLANTS;

EID: 0033220755     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/S0029-5493(99)00170-3     Document Type: Article

References (55)

1. Guide for making a condition survey of concrete in-service. Proc. Am. Concrete Inst. 65(11):1968;905-918.
2. American Concrete Institute, 1971. Building Code Requirements for Reinforced Concrete, ACI Standard 318-71, Detroit, MI, November.
3. American Concrete Institute, 1990. Code Requirements for Nuclear Safety Related Concrete Structures, ACI Standard 349-85(90), Detroit, MI.
4. Guide for evaluation of concrete structures prior to rehabilitation. ACI Mater. J. 90(5):1993;479-498.
5. American Concrete Institute, 1996. Evaluation of existing nuclear safety-related concrete structures, ACI 349.3R-96, Detroit, MI, March.
6. American Society of Civil Engineers, 1991. Guidelines for Structural Condition Assessment of Existing Buildings, ANSI/ASCE 11-90, New York, NY, August 1.
7. American Society of Mechanical Engineers, 1995. Requirements for Class CC concrete components of light-water cooled plants, Section XI, Subsection IWL. In: American Society of Mechanical Engineers Boiler and Pressure Vessel Code, New York, 1995 (1992 edition with Addenda).
8. American Society for Testing and Materials, 1990a. ASTM Protective Coatings Standards for Use in Nuclear Power Plants, Philadelphia, PA.
9. American Society for Testing and Materials, 1990b. Manual on Maintenance of Coatings for Nuclear Power Plants, Manual MNL 8, Philadelphia, PA.
10. Ashar H., Naus D.J., Tan C.P. Prestressed concrete in U.S. nuclear power plants (part 1). Concrete Int. 16(5):1994a;30-34.
11. Ashar H., Tan C.P., Naus D.J. Prestressed concrete in U.S. nuclear power plants (part 2). Concrete Int. 16(6):1994b;58-61.
12. Ashar, H., Jeng, D., 1990. Effectiveness of in-service inspection requirements of prestressed concrete containments - U.S. experience. Proc. of Second International Conference on Containment Design and Operation, Toronto, Ontario, Canada, 1990.
13. Barda F., Hanson J.M., Corley W.G. Shear strength of low-rise walls with boundary element. Reinforced Concrete Structures in Seismic Zones, ACI SP-53. 1977;1977 American Concrete Institute, Detroit, MI.
14. Cardenas A.E. et al. Design provisions for shear walls. J. Am. Concrete Inst. 70(3):1973;221-230.
15. Chen W.F., Han D.J. Plasticity for Structural Engineers. 1988;Spring-Vartag, New York.
16. Clifton J.R. Predicting the Remaining Service Life of Concrete, NISTIR 4712. 1991;U.S. Department of Commerce, National Institute of Standards and Technology, Gaithersburg, MD.
17. Durable Concrete Structures - Design Guide. 1992;Thomas Telford Services Publisher, London.
18. Dawson P., Wilson M.J.M. Surveillance Data for PCPVs at Wylfa, Hartlepool and Heysham I Power Stations, Report No. 1302/92/5957. 1993;R & D Division, Taywood Engineering Ltd, London, UK.
19. Electric Power Research Institute, 1994a. Class I Structures License Renewal Industry Report: Revision 1, EPRI TR-103842 (NUMARC 90-06), Palo Alto, CA, July.
20. Electric Power Research Institute, 1994b. PWR Containment Structures License Renewal Industry Report: Revision 1, EPRI TR-103835, Palo Alto, CA, July.
21. Electric Power Research Institute, 1994c. BWR Containments License Renewal Industry Report; Revision 1, EPRI TR-103840, Palo Alto, CA, July.
22. Ellingwood B.R., Mori Y. Probabilistic methods for condition assessment and life prediction of concrete structures in nuclear power plants. Nucl. Eng. Design. 142:1993;155-166.
23. Ellingwood, B.R. and Song, J., 1996. Impact of Structural Aging on Seismic Risk Assessment of Reinforced Concrete Structures in Nuclear Power Plants, NUREG/CR-6425, The Johns Hopkins University, Baltimore, MD, March.
24. Gregor F.E., Hookham C.J. Remnant life preservation of LWR plant structures. Transactions of the 12th International Conference on Structural Mechanics in Reactor Technology, August 15-20, 1993, Stuttgart, Germany, Paper DH06/2. 1993;453-459 Elsevier, Amsterdam, The Netherlands.
25. Hartley J., Bamforth P.B. Collation of Survey Data and Review of Durability Assessment of Reinforced Concrete Structures at Nuclear Power Stations in the UK, Report 1303/92/6163. 1993;R & D Division, Taywood Engineering Ltd, London, UK.
26. Hill H.T. Concrete Containment Posttensioning System Aging Study, ORNL/NRC/LTR-95/13. 1995;Lockheed Martin Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN.
27. Hookham, C.J., 1991. Structural Aging Assessment Methodology for Concrete Structures in Nuclear Power Plants, ORNL/NRC/LTR-90/17, Martin Marietta Energy Systems, Inc., Oak Ridge National LaboratoryOak Ridge, TN, March.
28. Hookham, C.J., 1995. In-Service Inspection Guidelines for Concrete Structures in Nuclear Power Plants, ORNL/NRC/LTR-95/14, Lockheed Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN, August.
29. Hulot M. et al. State-of-the-Art Technology for Measuring and Controlling Very Low-Level Radioactivity in Relation to Decommissioning of Nuclear Plants, EUR 10643. 1986;Directorate-General Science, Commission of European Communities, Luxembourg.
30. Krauss, P.D., 1994. Repair Materials and Techniques for Concrete Structures in Nuclear Power Plants, ORNL/NRC/LTR-93/28, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN, March.
31. MacGregor J.G., Mirza A., Ellingwood B.R. Statistical analysis of resistance of reinforced and prestressed concrete members. J. Am. Concrete Inst. 80(3):1983;167-176.
32. Madsen H., Sorenson J.D., Olesen R. Optimal inspection planning for fatigue damage of offshore structures. Proceedings of ICOSSAR '89. III:1989;2099-2106 American Society of Civil Engineers, New York, NY.
33. Mori Y., Ellingwood B.R. Maintaining reliability of concrete structures. I. Role of inspection/repair. J. Struct. Eng. 120(3):1994a;824-845.
34. Mori Y., Ellingwood B.R. Maintaining reliability of concrete structures. II. Optimum inspection/repair strategies. J. Struct. Eng. 120(3):1994b;846-862.
35. Mori Y., Ellingwood B.R. Reliability Assessment of Degrading Concrete Shear Walls, ORNL/NRC/LTR-94/6. 1994c;Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN.
36. Mori, Y., 1992. Reliability-Based Condition Assessment and Life Prediction of Concrete Structures, Thesis, The Johns Hopkins University, Baltimore, MD (in partial fulfillment of the requirements for the degree of Doctor of Philosophy).
37. Naus, D.J., Oland, C.B., Ellingwood, B.R., 1996. Report on Aging of Nuclear Power Plant Concrete Structures, NUREG/CR-6426 (ORNL/TM-13148), Lockheed Martin Energy Research, Corp., Oak Ridge National Laboratory, Oak Ridge, TN, March.
38. Naus, D.J., 1984. Concrete Component Aging and Its Significance Relative to Life Extension of Nuclear Power Plants, NUREG/CR-4652 (ORNL/TM-10035), Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN, September.
39. Nuclear Energy Agency, 1994. Nuclear Safety Research in OECD Countries, Senior Group of Experts on Safety Research, Issy-les-Moulineaux, France.
40. Oland C.B. The Structural Materials Information Center and Its Potential Applications, ORNL/NRC/LTR-92/8. 1992;1992 Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN.
41. Oland C.B., Naus D.J. Summary of Materials Contained in the Structural Materials Information Center, ORNL/NRC/LTR-94/22. 1994;Oak Ridge National Laboratory, Martin Marietta Energy Systems, Inc., Oak Ridge, TN.
42. Perenchio W.F. The condition survey. Concrete Int. 11(1):1989;59-62.
43. Price W.F. et al. Review of European Repair Practice for Corrosion Damaged Reinforced Concrete, Report No. 1303/91/5823. 1993;R & D Division, Taywood Engineering Ltd, London, UK.
44. Refai, T.M., Lim, M.K., 1991. In-Service Inspection and Structural Integrity Assessment Methods for Nuclear Power Plant Concrete Structures, ORNL/NRC/LTR-90/29, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN, September.
45. Regourd M. Physico-chemical and biological processes related to concrete. Durability of Concrete Structures, Bulletin d'Information 152. 1984;Comité Euro-International du Béton, Lausanne, Switzerland.
46. Shiraishi I., Shirai N., Murakami T., Minami K. Macroscopic models for R/C shear walls. Proc. of Structural Congress, Structural Design, Analysis, and Testing. 1989;271-280 American Society of Civil Engineers, New York, NY.
47. Shohara, R., Shirai, N., Noguchi, H., 1989. Verification of macroscopic models for R/C walls. In: Proc. of Structural Congress, Structural Design, Analysis, and Testing, American Society of Civil Engineers, New York, NY, 281-290.
48. Snyder K.A. et al. Nondestructive Evaluation of the In-Place Compressive Strength of Concrete Based Upon Limited Destructive Testing, NISTIR 4874. 1992;U.S. Department of Commerce, National Institute of Standards and Technology, Gaithersburg, MD.
49. Swiat W.J. et al. State-of-the-Art Report - Corrosion of Steel in Concrete, ORNL/NRC/LTR-93/2. 1993;Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, Oak Ridge, TN.
50. U.S. Nuclear Regulatory Commission, 1983. PRA Procedures Guide, NUREG/CR-2300, Vols. 1-2, Washington, DC.
51. U.S. Nuclear Regulatory Commission, 1996. Nuclear Regulatory Commission Information Digest, NUREG-1350, Vol. 8. Division of Budget and Analysis, Office of the Controller, Washington, DC, July.
52. Vecchio F.P., Collins M.P. The modified compression-field theory for reinforced concrete elements subjected to shear. J. Am. Concrete Inst. 83(2):1986;219-231.
53. Washa G.W., Saemann J.C., Cramer S.M. Fifty-year properties of concrete made in 1937. ACl Mater. J. 86(4):1989;367-371.
54. Watanabe F., Ichinose T. Strength and ductility design of RC members subjected to combined bending and shear. Hsu T.C.C., Mau S.T. Concrete Shear in Earthquake. 1992;429-438 Elsevier, New York, NY.
55. Yang J. Application of reliability methods to fatigue, quality assurance, and maintenance. Proceedings of ICOSSAR '93. I:1994;3-18 A.A. Balkema, Rotterdam, The Netherlands.