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Volumn 346, Issue , 1997, Pages 85-94

Development of a methodology for the assessment of shallow-flaw fracture in nuclear reactor pressure vessels

Author keywords

[No Author keywords available]

Indexed keywords

CRACK INITIATION; FRACTURE MECHANICS; FRACTURE TESTING; FRACTURE TOUGHNESS; NUCLEAR REACTORS; PRESSURE VESSELS; RELAXATION PROCESSES; STRESSES; YIELD STRESS;

EID: 0030651113     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article
Times cited : (12)

References (19)
  • 1
    • 0003701462 scopus 로고    scopus 로고
    • Version 5.5, Hibbitt, Karlson, and Sorenson, Inc., Providence, Rhode Island
    • ABAQUS Theory Manual, 1996, Version 5.5, (Hibbitt, Karlson, and Sorenson, Inc., Providence, Rhode Island.
    • (1996) ABAQUS Theory Manual
  • 2
    • 0021610937 scopus 로고
    • The Influence of Multiaxial Stress States on Characteristic Parameters for Cleavage Fracture in the Elastic-Plastic Range
    • Aurich, D. et al., 1984, "The Influence of Multiaxial Stress States on Characteristic Parameters for Cleavage Fracture in the Elastic-Plastic Range," pp. 345-356 in Proceedings International Conference Applied Fracture Mechanics to Material and Structure.
    • (1984) Proceedings International Conference Applied Fracture Mechanics to Material and Structure , pp. 345-356
    • Aurich, D.1
  • 3
    • 0029427369 scopus 로고
    • Assessment of the Fracture Behavior of Weld Material from a Full-Thickness Clad RPV Shell Segment
    • ASME
    • Bass, B. R., Keeney, J. A. and McAfee, W. J., 1995, "Assessment of the Fracture Behavior of Weld Material from a Full-Thickness Clad RPV Shell Segment," PVP-Vol. 304, Fatigue and Fracture Mechanics in Pressure Vessels and Piping, ASME, pp. 299-311.
    • (1995) Fatigue and Fracture Mechanics in Pressure Vessels and Piping , vol.304 PVP , pp. 299-311
    • Bass, B.R.1    Keeney, J.A.2    McAfee, W.J.3
  • 4
    • 0030650111 scopus 로고    scopus 로고
    • Determination of Cladding Effects on Shallow-Flaw Fracture Toughness of Reactor Pressure Vessel Steel under Prototypic Biaxial Loading
    • Nice, France, May 26-30, 1997.
    • Bass, B. R. et al., 1997, "Determination of Cladding Effects on Shallow-Flaw Fracture Toughness of Reactor Pressure Vessel Steel under Prototypic Biaxial Loading", to be presented at the 5th International Conference on Nuclear Engineering, Nice, France, May 26-30, 1997.
    • (1997) 5th International Conference on Nuclear Engineering
    • Bass, B.R.1
  • 8
    • 5544327352 scopus 로고    scopus 로고
    • Development of Heat-Treating Specification for Surrogate Irradiated Base Material
    • USNRC Report NUREG/CR-4219 (ORNL/TM-9593/V12&N1), Oak Ridge National Laboratory
    • McAfee, W. J. and Penneli, W. E., 1996, "Development of Heat-Treating Specification for Surrogate Irradiated Base Material," pp. 5 in Heavy-Section Steel Technology Program Semiannual Progress Report for October 1994-March 1995, USNRC Report NUREG/CR-4219 (ORNL/TM-9593/V12&N1), Vol. 12, No. 1, Oak Ridge National Laboratory.
    • (1996) Heavy-Section Steel Technology Program Semiannual Progress Report for October 1994-March 1995 , vol.12 , Issue.1 , pp. 5
    • McAfee, W.J.1    Penneli, W.E.2
  • 13
    • 0026910140 scopus 로고
    • Heavy-Section Steel Technology Program - Fracture Issues
    • Pennell, W. E., 1992, "Heavy-Section Steel Technology Program - Fracture Issues", pp. 255-264 in Journal of Pressure Vessel Technology, Vol. 114.
    • (1992) Journal of Pressure Vessel Technology , vol.114 , pp. 255-264
    • Pennell, W.E.1
  • 14
    • 38249000705 scopus 로고
    • Heavy-Section Steel Technology Program: Recent developments in crack initiation and arrest research
    • Pennell, W. E., 1993, "Heavy-Section Steel Technology Program: recent developments in crack initiation and arrest research," pp. 255-266 in Nuclear Engineering and Design, Vol. 142.
    • (1993) Nuclear Engineering and Design , vol.142 , pp. 255-266
    • Pennell, W.E.1
  • 15
    • 0030384929 scopus 로고    scopus 로고
    • Preliminary Assessment of the Effects of Biaxial Loading on Reactor Pressure Vessel Structural-Integrity-Assessment Technology
    • New Orleans, LA, March 10-14, 1996
    • Pennell, W. E. et al., 1996, "Preliminary Assessment of the Effects of Biaxial Loading on Reactor Pressure Vessel Structural-Integrity-Assessment Technology," Proceedings of 4th ASME/JSME International Conference in Nuclear Engineering, New Orleans, LA, March 10-14, 1996.
    • (1996) Proceedings of 4th ASME/JSME International Conference in Nuclear Engineering
    • Pennell, W.E.1
  • 18
    • 0343079498 scopus 로고
    • Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, USNRC Report NUREG/CR-6132 (ORNL/TM-12498)
    • Theiss, T. J. et al., 1994, Martin Marietta Energy Systems, Inc., Oak Ridge National Laboratory, "Initial Results of the Influence of Biaxial Loading on Fracture Toughness," USNRC Report NUREG/CR-6132 (ORNL/TM-12498).
    • (1994) Initial Results of the Influence of Biaxial Loading on Fracture Toughness
    • Theiss, T.J.1
  • 19
    • 0345116013 scopus 로고
    • Material Ductility and Fracture Toughness of Metals
    • Hyoto, Japan, August 15-20, 1971, The Society of Materials Science, Japan
    • Weiss, V., 1972, "Material Ductility and Fracture Toughness of Metals," Proceedings of the International Conference on Mechanical Behavior of Materials, Hyoto, Japan, August 15-20, 1971, The Society of Materials Science, Japan.
    • (1972) Proceedings of the International Conference on Mechanical Behavior of Materials
    • Weiss, V.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.