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Volumn 373, Issue , 1998, Pages 387-395

The inclusion of weld residual stress in fracture margin assessments of embrittled nuclear reactor pressure vessels

Author keywords

[No Author keywords available]

Indexed keywords

FAILURE ANALYSIS; FINITE ELEMENT METHOD; FRACTURE; PRESSURIZED WATER REACTORS; RESIDUAL STRESSES; STRESS CONCENTRATION; THERMAL STRESS; WELDS;

EID: 0031642220     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Article
Times cited : (8)

References (17)
  • 3
    • 3342917048 scopus 로고    scopus 로고
    • Title 10, Section 50.61 and Appendix G
    • Code of Federal Regulations, Title 10, Part 50, Section 50.61 and Appendix G.
    • Code of Federal Regulations , Issue.50 PART
  • 4
    • 0005552070 scopus 로고
    • Radiation Embrittlement of Reactor Vessel Materials
    • May
    • U.S. Nuclear Regulatory Commission, Regulatory Guide 1.99, Revision 2, "Radiation Embrittlement of Reactor Vessel Materials", May, 1988.
    • (1988) Regulatory Guide 1.99, Revision 2
  • 5
    • 0003798138 scopus 로고
    • Hibbit, Karlsson & Sorenson, Inc., Providence, Rhode Island
    • ABAQUS User Manual, Hibbit, Karlsson & Sorenson, Inc., Providence, Rhode Island (1995).
    • (1995) ABAQUS User Manual
  • 6
    • 0029426596 scopus 로고
    • Validation of FAVOR Code Linear Elastic Fracture Solutions for Finite-Length Flaw Geometries
    • ASME
    • T.L. Dickson, "Validation of FAVOR Code Linear Elastic Fracture Solutions for Finite-Length Flaw Geometries", PVP-Vol. 304, Fatigue and Fracture Mechanics in Pressure Vessels and Piping, ASME 1995.
    • (1995) Fatigue and Fracture Mechanics in Pressure Vessels and Piping , vol.304 PVP-VOL.
    • Dickson, T.L.1
  • 7
    • 3343008502 scopus 로고
    • PVRC Recommendations on Toughness Requirements of Ferritic Materials
    • August
    • PVRC Recommendations on Toughness Requirements of Ferritic Materials, Welding Research Council Bulletin 175, August 1972.
    • (1972) Welding Research Council Bulletin 175
  • 9
    • 0030182161 scopus 로고    scopus 로고
    • Development of Criteria for Assessment of Reactor Vessels with Low Upper Shelf Fracture Toughness
    • prepared by the Working Group on Flaw Evaluation of ASME Section XI and published by the Pressure Vessel Research Council of the Welding Research Council, Inc., New York, July
    • WRC Bulletin 413, Development of Criteria for Assessment of Reactor Vessels with Low Upper Shelf Fracture Toughness, prepared by the Working Group on Flaw Evaluation of ASME Section XI and published by the Pressure Vessel Research Council of the Welding Research Council, Inc., New York, July, 1996.
    • (1996) WRC Bulletin 413
  • 10
    • 0043212728 scopus 로고
    • Ic Curve
    • ASME PVP June 1991
    • Ic Curve, ASME PVP volume 213/MPC-Vol. 32, Pressure Vessel Integrity, 1991, pp. 141-148, June 1991.
    • (1991) Pressure Vessel Integrity , vol.32-213 MPC-VOL. , pp. 141-148
    • McCabe, D.E.1
  • 12
    • 3342882355 scopus 로고
    • Nuclear Regulatory HSST and HSSI Programs, Thermal Reactor Safety Assessment
    • held at Manchester, England. May 23-26, published by Thomas Tellford, London
    • W. E. Pennell et al., Nuclear Regulatory HSST and HSSI Programs, Thermal Reactor Safety Assessment, Proceedings of the Conference organized by the British Nuclear Energy Society, held at Manchester, England. May 23-26, 1994, published by Thomas Tellford, London.
    • (1994) Proceedings of the Conference Organized by the British Nuclear Energy Society
    • Pennell, W.E.1
  • 17
    • 3342929227 scopus 로고
    • Cladding Stresses in a Pressurized Water Reactor Vessel following Application of the Stainless Steel Cladding, Heat Treatment and Initial Service
    • ASME, ASME
    • B. R. Ganta, D. J. Ayres, and P. J. Hijeck, "Cladding Stresses in a Pressurized Water Reactor Vessel following Application of the Stainless Steel Cladding, Heat Treatment and Initial Service,", ASME PVP-Vol. 213/MPC-Vol. 32, Pressure Vessel Integrity, ASME 1991.
    • (1991) Pressure Vessel Integrity , vol.32-213 PVP-VOL. AND MPC-VOL.
    • Ganta, B.R.1    Ayres, D.J.2    Hijeck, P.J.3


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.