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Volumn 118, Issue 4, 1996, Pages 441-446

Reliability of steam generator tubes with axial cracks

Author keywords

[No Author keywords available]

Indexed keywords

CRACK PROPAGATION; CRACKS; FAILURE (MECHANICAL); FRACTURE MECHANICS; INSPECTION; MAINTENANCE; NONDESTRUCTIVE EXAMINATION; NUCLEAR POWER PLANTS; PROBABILITY; RELIABILITY; RESIDUAL STRESSES; STEAM GENERATORS;

EID: 0030289917     PISSN: 00949930     EISSN: 15288978     Source Type: Journal    
DOI: 10.1115/1.2842211     Document Type: Article
Times cited : (17)

References (16)
  • 2
    • 1542547959 scopus 로고
    • Numerical Methods in Probabilistic Fracture Mechanics
    • J. W. Provan, Martinus Nijhoff Publishers
    • Bruckner, A., 1987, “Numerical Methods in Probabilistic Fracture Mechanics,” Probabilistic Fracture Mechanics and Reliability, ed., J. W. Provan, Martinus Nijhoff Publishers, pp. 351-386.
    • (1987) Probabilistic Fracture Mechanics and Reliability , pp. 351-386
    • Bruckner, A.1
  • 4
    • 0028408643 scopus 로고
    • Application of First and Second Order Reliability Methods in the Safety Assessment of Cracked Steam Generator Tubes
    • Cizelj, L., Mavko, B., and Riesch-Oppermann, H., 1994, “Application of First and Second Order Reliability Methods in the Safety Assessment of Cracked Steam Generator Tubes,” Nuclear Engineering and Design, Vol. 147, p. 359-368.
    • (1994) Nuclear Engineering and Design , vol.147 , pp. 359-368
    • Cizelj, L.1    Mavko, B.2    Riesch-Oppermann, H.3
  • 6
    • 0006185845 scopus 로고
    • Crack Stability Criteria in Steam Generator Tubes
    • F. H. Wittmann, Trans of 9th Int Conf on SMiRT, Laussane, Switzerland, Vol. D
    • Cochet, B., and Flesch, B., 1989, “Crack Stability Criteria in Steam Generator Tubes,” Experience with Structures and Components in Operating Reactors, ed., F. H. Wittmann, Trans of 9th Int Conf on SMiRT, Laussane, Switzerland, Vol. D, pp. 413-419.
    • (1989) Experience with Structures and Components in Operating Reactors , pp. 413-419
    • Cochet, B.1    Flesch, B.2
  • 8
    • 85025186295 scopus 로고
    • NEA-CSNl-UNIPEDE Specialist Meeting on Operating Experience With Steam Generators, Brussels, Belgium
    • Dobbeni, D., 1991, “Eddy Current Inspection Methodology,” NEA-CSNl-UNIPEDE Specialist Meeting on Operating Experience With Steam Generators, Brussels, Belgium.
    • (1991) Eddy Current Inspection Methodology
    • Dobbeni, D.1
  • 9
    • 85025181386 scopus 로고
    • International Joint Power Generation Conference on PWR Steam Generator Tube Repair Criteria and Inservice Inspection Requirements, Kansas City, October 17-22, Paper No. 93-JPGC-NE-2
    • Dvoršek, T., Cizelj, L., and Mavko, B., 1993, “Recent Experience with KrSko Steam Generators,” International Joint Power Generation Conference on PWR Steam Generator Tube Repair Criteria and Inservice Inspection Requirements, Kansas City, October 17-22, Paper No. 93-JPGC-NE-2.
    • (1993) Recent Experience with Krsko Steam Generators
    • Dvoršek, T.1    Cizelj, L.2    Mavko, B.3
  • 10
    • 0017010136 scopus 로고
    • Ductile Fracture Theories for Pressurized Pipes and Containers
    • Erdogan, F., 1976, “Ductile Fracture Theories for Pressurized Pipes and Containers,” International Journal of Pressure Vessels and Piping, Vol. 4, pp. 253-283.
    • (1976) International Journal of Pressure Vessels and Piping , vol.4 , pp. 253-283
    • Erdogan, F.1
  • 12
    • 0026868613 scopus 로고
    • Failure Probability of Axially Cracked Steam Generator Tubes: A Probabilistic Fracture Mechanics Model
    • Mavko, B., and Cizelj, L., 1992, “Failure Probability of Axially Cracked Steam Generator Tubes: A Probabilistic Fracture Mechanics Model,” Nuclear Technology, Vol. 98, No. 2, pp. 171-177.
    • (1992) Nuclear Technology , vol.98 , Issue.2 , pp. 171-177
    • Mavko, B.1    Cizelj, L.2
  • 14
    • 0004610181 scopus 로고
    • Application of Probabilistic Fracture Mechanics to Optimize the Maintenance of PWR Steam Generator Tubes
    • Pitner, P., Riffard, T., Granger, B., and Flesch, B., 1993, “Application of Probabilistic Fracture Mechanics to Optimize the Maintenance of PWR Steam Generator Tubes,” Nuclear Engineering and Design, Vol. 142, p. 89-100.
    • (1993) Nuclear Engineering and Design , vol.142 , pp. 89-100
    • Pitner, P.1    Riffard, T.2    Granger, B.3    Flesch, B.4


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.