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Volumn 388, Issue , 1999, Pages 79-89

Revisiting the Integrated Pressurized Thermal Shock studies of an aging pressurized water reactor

Author keywords

[No Author keywords available]

Indexed keywords

AGING OF MATERIALS; CRACK PROPAGATION; FRACTURE MECHANICS; MATHEMATICAL MODELS; PRESSURIZED WATER REACTORS; PROBABILITY; STRUCTURAL ANALYSIS;

EID: 0033308407     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (16)

References (21)
  • 1
    • 0342654499 scopus 로고    scopus 로고
    • Code of Federal Regulations, Title 10, Part 50, Section 50.61 and Appendix G.
    • Code of Federal Regulations, Title 10, Part 50, Section 50.61 and Appendix G.
  • 8
    • 0000001656 scopus 로고
    • An overview of FAVOR: A fracture analysis code for nuclear reactor pressure vessels
    • Porto Alegre, Brazil, August
    • T. L. Dickson, An Overview of FAVOR: A Fracture Analysis Code for Nuclear Reactor Pressure Vessels, transactions of the 13th International Conference on Structural Mechanics in Reactor Technology (SMiRT 13), Volume IV, pp 701-706, Porto Alegre, Brazil, August, 1995.
    • (1995) 13th International Conference on Structural Mechanics in Reactor Technology (SMiRT 13) , vol.4 , pp. 701-706
    • Dickson, T.L.1
  • 12
    • 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
    • Dickson, T.L.1
  • 13
    • 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
  • 14
    • 0004822176 scopus 로고    scopus 로고
    • NUREG-1511, U.S. Nuclear Regulatory Commission, December, 1994, NUREG-1511, Supplement 1, October, 1996; RVID Version 2.0, August
    • Reactor Vessel Integrity Database, NUREG-1511, U.S. Nuclear Regulatory Commission, December, 1994, NUREG-1511, Supplement 1, October, 1996; RVID Version 2.0, August, 1997.
    • (1997) Reactor Vessel Integrity Database
  • 18
    • 23544473726 scopus 로고    scopus 로고
    • Inclusion of embedded flaws in pressurized thermal shock analyses of nuclear reactor pressure vessels
    • ASME
    • T. L. Dickson and F. A. Simonen, Inclusion of Embedded Flaws in Pressurized Thermal Shock Analyses of Nuclear Reactor Pressure Vessels, PVP-Vol. 46, Fatigue and Fracture, ASME 1997.
    • (1997) Fatigue and Fracture , vol.46 PVP
    • Dickson, T.L.1    Simonen, F.A.2


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.