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Volumn 228, Issue 1-3, 2004, Pages 55-72

Methods for assessing NPP containment pressure boundary integrity

Author keywords

[No Author keywords available]

Indexed keywords

AGING OF MATERIALS; CODES (STANDARDS); CONCRETES; CORROSION; INSPECTION; PRESSURE EFFECTS; PRESSURE VESSELS; REGULATORY COMPLIANCE; RELIABILITY; STEEL; STRUCTURAL ANALYSIS;

EID: 0442327415     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2003.06.024     Document Type: Conference Paper
Times cited : (7)

References (44)
  • 1
    • 0010022819 scopus 로고
    • Building code requirements for reinforced concrete
    • ACI Committee 318, American Concrete Institute, Detroit, Michigan
    • ACI, 1971. Building code requirements for reinforced concrete. In: ACI Standard 318-71. ACI Committee 318, American Concrete Institute, Detroit, Michigan.
    • (1971) ACI Standard , vol.318 , Issue.71
  • 3
    • 0000866844 scopus 로고
    • The long-range detection of corrosion in pipes using Lamb waves
    • Plenum Press
    • Alleyne, D.N., Cawley, P., 1995. The long-range detection of corrosion in pipes using Lamb waves. In: Review of Progress in Quantitative NDE. Plenum Press, pp. 2075-2080.
    • (1995) Review of Progress in Quantitative NDE , pp. 2075-2080
    • Alleyne, D.N.1    Cawley, P.2
  • 4
    • 0010581946 scopus 로고
    • ANSI/ANS-56.8. American Nuclear Society, La Grange Park, IL
    • ANS, 1994. Containment System Leakage Testing Requirements, ANSI/ANS-56.8. American Nuclear Society, La Grange Park, IL.
    • (1994) Containment System Leakage Testing Requirements
  • 6
    • 0442320654 scopus 로고
    • Rules for construction of unfired pressure vessels
    • American Society of Mechanical Engineers, New York, NY
    • ASME, 1965. Rules for construction of unfired pressure vessels. In: ASME Boiler and Pressure Vessel Code, Section VIII. American Society of Mechanical Engineers, New York, NY.
    • (1965) ASME Boiler and Pressure Vessel Code, Section VIII
  • 7
    • 0041974289 scopus 로고    scopus 로고
    • Rules for construction of nuclear power plant components
    • Division 1, Subsection NE, Class MC Components. American Society of Mechanical Engineers, New York, NY
    • ASME, 2001. Rules for construction of nuclear power plant components. In: ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsection NE, Class MC Components. American Society of Mechanical Engineers, New York, NY.
    • (2001) ASME Boiler and Pressure Vessel Code, Section III
  • 9
    • 0343455052 scopus 로고    scopus 로고
    • Analyses of containment structures with corrosion damage
    • NUREG/CP-0157. U.S. Nuclear Regulatory Commission, Washington, DC
    • Cherry, J.L., 1997. Analyses of containment structures with corrosion damage. In: Proceedings of 24th Water Reactor Safety Information Meeting, NUREG/CP-0157. U.S. Nuclear Regulatory Commission, Washington, DC.
    • (1997) Proceedings of 24th Water Reactor Safety Information Meeting
    • Cherry, J.L.1
  • 10
    • 0029709235 scopus 로고    scopus 로고
    • Guided waves in water loaded hollow cylinder
    • Cho Y., Rose J.L. Guided waves in water loaded hollow cylinder. Nondestructive Testing Evaluat. 12:1996;323-339.
    • (1996) Nondestructive Testing Evaluat. , vol.12 , pp. 323-339
    • Cho, Y.1    Rose, J.L.2
  • 11
    • 0028386589 scopus 로고
    • Probability-based codified design: Past accomplishments and future challenges
    • Ellingwood B.R. Probability-based codified design: past accomplishments and future challenges. Struct. Safety. 13(3):1994;159-176.
    • (1994) Struct. Safety , vol.13 , Issue.3 , pp. 159-176
    • Ellingwood, B.R.1
  • 13
    • 0032318526 scopus 로고    scopus 로고
    • Issues related to structural aging in probabilistic risk analysis of nuclear power plants
    • Ellingwood B.R. Issues related to structural aging in probabilistic risk analysis of nuclear power plants. Reliability Eng. Syst. Safety. 62(3):1998;171-183.
    • (1998) Reliability Eng. Syst. Safety , vol.62 , Issue.3 , pp. 171-183
    • Ellingwood, B.R.1
  • 14
    • 0022131895 scopus 로고
    • Probabilistic descriptions of resistance of safety-related structures in nuclear plants
    • Ellingwood B.R., Hwang H. Probabilistic descriptions of resistance of safety-related structures in nuclear plants. Nucl. Eng. Des. 88(2):1986;169-178.
    • (1986) Nucl. Eng. Des. , vol.88 , Issue.2 , pp. 169-178
    • Ellingwood, B.R.1    Hwang, H.2
  • 15
    • 0033326128 scopus 로고    scopus 로고
    • Fragility modeling of a steel containment with localized corrosion
    • ASME PVP-385. American Society of Mechanical Engineers, New York, NY
    • Ellingwood, B.R., Cherry, J.L., Naus, D.J., 1999. Fragility modeling of a steel containment with localized corrosion. In: Proceedings of Computer Technology-1999, ASME PVP-385. American Society of Mechanical Engineers, New York, NY, pp. 101-105.
    • (1999) Proceedings of Computer Technology-1999 , pp. 101-105
    • Ellingwood, B.R.1    Cherry, J.L.2    Naus, D.J.3
  • 20
    • 0442320667 scopus 로고    scopus 로고
    • Long-range volumetric inspection of tubing using the magnetostrictive sensor technique
    • Jackson Hole, Wyoming
    • Kwun, H., 1996. Long-range volumetric inspection of tubing using the magnetostrictive sensor technique. In: Fourth EPRI Balance of Plant Nondestructive Evaluation Symposium. Jackson Hole, Wyoming.
    • (1996) Fourth EPRI Balance of Plant Nondestructive Evaluation Symposium
    • Kwun, H.1
  • 22
    • 0442273594 scopus 로고    scopus 로고
    • Engineering Science and Mechanics Department, The Pennsylvania State University, University Park, Pennsylvania
    • Li, J., Rose, J.L., 2000. Guided Wave Inspection of Containment Structures. Engineering Science and Mechanics Department, The Pennsylvania State University, University Park, Pennsylvania.
    • (2000) Guided Wave Inspection of Containment Structures
    • Li, J.1    Rose, J.L.2
  • 23
    • 0021610934 scopus 로고
    • Containment integrity of SEP plants under combined loads
    • Ucciferro, J. (Ed.), American Society of Civil Engineers, New York, NY
    • Lo, T., et al., 1984. Containment integrity of SEP plants under combined loads. In: Ucciferro, J. (Ed.), Proceedings of the ASCE Conference on Structural Engineering in Nuclear Facilities. American Society of Civil Engineers, New York, NY.
    • (1984) Proceedings of the ASCE Conference on Structural Engineering in Nuclear Facilities
    • Lo, T.1
  • 26
    • 0442320656 scopus 로고    scopus 로고
    • Condition assessment of concrete structures in nuclear power plants
    • Report No. 19. International Union of Testing and Research Laboratories for Materials and Structures (RILEM), Cachan Cedex, France
    • Naus, D.J., Hookham, C.J., 1999. Condition assessment of concrete structures in nuclear power plants. In: State-Of-The-Art: Considerations for Use In Managing the Aging of Nuclear Power Plant Concrete Structures, Report No. 19. International Union of Testing and Research Laboratories for Materials and Structures (RILEM), Cachan Cedex, France.
    • (1999) State-Of-The-Art: Considerations for Use In Managing the Aging of Nuclear Power Plant Concrete Structures
    • Naus, D.J.1    Hookham, C.J.2
  • 28
    • 0033349538 scopus 로고    scopus 로고
    • Inspection of nuclear power plant containment structures
    • Norris W.E., Naus D.J., Graves H.L. III Inspection of nuclear power plant containment structures. Nucl. Eng. Des. 192:1999;303-329.
    • (1999) Nucl. Eng. Des. , vol.192 , pp. 303-329
    • Norris, W.E.1    Naus, D.J.2    Graves III, H.L.3
  • 29
    • 0442305025 scopus 로고
    • General Design Criteria for nuclear power plants
    • Appendix A to Part 50 of Title 10 "Energy," Washington, DC
    • OFR, 1995b. General Design Criteria for nuclear power plants. In: Office of Federal Register, Appendix A to Part 50 of Title 10 "Energy," Washington, DC.
    • (1995) Office of Federal Register
  • 30
    • 0442289156 scopus 로고
    • Primary reactor containment leakage testing for water-cooled power reactors
    • Appendix J in 10 CFR Part 50, Office of Federal Register, Washington, DC
    • OFR, 1995a. Primary reactor containment leakage testing for water-cooled power reactors. In: Code of Federal Regulations, Appendix J in 10 CFR Part 50, Office of Federal Register, Washington, DC.
    • (1995) Code of Federal Regulations
  • 31
    • 0442305021 scopus 로고    scopus 로고
    • Proposed rules
    • Washington, DC
    • OFR, 2001. Proposed rules. In: Office of Federal Register, vol. 66, no. 150, Washington, DC, pp. 40626-40640.
    • (2001) Office of Federal Register , vol.66 , Issue.150 , pp. 40626-40640
  • 35
    • 0033308849 scopus 로고    scopus 로고
    • Multimode guided wave inspection of piping using comb transducers
    • Quarry M., Rose J.L. Multimode guided wave inspection of piping using comb transducers. Mater. Evaluat. 57(10):1999;1089-1090.
    • (1999) Mater. Evaluat. , vol.57 , Issue.10 , pp. 1089-1090
    • Quarry, M.1    Rose, J.L.2
  • 37
    • 0030287880 scopus 로고    scopus 로고
    • Ultrasonic guided wave NDE for piping
    • Rose J.L., Jiao D., Spanner J. Jr. Ultrasonic guided wave NDE for piping. Mater. Evaluat. 54(11):1996;1310-1313.
    • (1996) Mater. Evaluat. , vol.54 , Issue.11 , pp. 1310-1313
    • Rose, J.L.1    Jiao, D.2    Spanner, J.Jr.3
  • 39
    • 0442320647 scopus 로고
    • Concrete containment
    • NUREG-0800. Directorate of Licensing, Washington, DC
    • USNRC, 1981b. Concrete containment. In: Regulatory Standard Review Plan, Section 3.8.1, NUREG-0800. Directorate of Licensing, Washington, DC.
    • (1981) Regulatory Standard Review Plan, Section 3.8.1
  • 40
    • 0442305038 scopus 로고
    • Concrete and steel internal structures of steel and concrete containments
    • NUREG-0800. Directorate of Licensing, Washington, DC
    • USNRC, 1981a. Concrete and steel internal structures of steel and concrete containments. In: Regulatory Standard Review Plan, Section 3.8.3, NUREG-0800. Directorate of Licensing, Washington, DC.
    • (1981) Regulatory Standard Review Plan, Section 3.8.3
  • 42
    • 85031587826 scopus 로고
    • Performance-Based Containment Leak-Test Program
    • U.S. Nuclear Regulatory Commission, Washington, DC
    • USNRC, 1995. Performance-Based Containment Leak-Test Program, Regulatory Guide 1.163. U.S. Nuclear Regulatory Commission, Washington, DC.
    • (1995) Regulatory Guide 1.163
  • 43
    • 84885307127 scopus 로고    scopus 로고
    • An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis
    • U.S. Nuclear Regulatory Commission, Washington, DC
    • USNRC, 1998. An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis, Regulatory Guide 1.174. U.S. Nuclear Regulatory Commission, Washington, DC.
    • (1998) Regulatory Guide 1.174
  • 44
    • 0010660987 scopus 로고
    • Current state of knowledge on the behavior of steel liners in concrete containments subjected to overpressurization loads
    • Von Riesemann W.A., Parks M.B. Current state of knowledge on the behavior of steel liners in concrete containments subjected to overpressurization loads. Nucl. Eng. Des. 157:1995;481-487.
    • (1995) Nucl. Eng. Des. , vol.157 , pp. 481-487
    • Von Riesemann, W.A.1    Parks, M.B.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.