메뉴 건너뛰기




Volumn , Issue , 2005, Pages 471-483

The effect of transients on the crack growth behavior of low alloy steels for pressure boundary components under light water reactor operating conditions

Author keywords

Environmentally assisted cracking; Low alloy steel; LWR; RPV; Transients

Indexed keywords

BOILING WATER REACTORS; CORROSION; FRACTURE MECHANICS; HEAT AFFECTED ZONE; HIGH TEMPERATURE EFFECTS; LIGHT WATER REACTORS; STEEL; STRESS ANALYSIS; TRANSIENTS; WELDING;

EID: 33745202370     PISSN: None     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper
Times cited : (12)

References (17)
  • 3
    • 33745220177 scopus 로고    scopus 로고
    • Crack growth behaviour of low alloy steels for pressure boundary components under transient light water reactor operating conditions
    • EU project CASTOC"
    • U. Ehrnstén, "Crack Growth Behaviour of Low Alloy Steels for Pressure Boundary Components Under Transient Light Water Reactor Operating Conditions", EU project CASTOC", Technical Report WP1, 2002.
    • (2002) Technical Report , vol.WP1
    • Ehrnstén, U.1
  • 4
    • 33745200616 scopus 로고    scopus 로고
    • Crack growth behaviour of low alloy steels for pressure boundary components under transient light water reactor operating conditions
    • EU project CASTOC"
    • J. Lapeña, D. Gómez-Briceño, "Crack Growth Behaviour of Low Alloy Steels for Pressure Boundary Components Under Transient Light Water Reactor Operating Conditions", EU project CASTOC", Technical Report WP2, (2003).
    • (2003) Technical Report , vol.WP2
    • Lapeña, J.1    Gómez-Briceño, D.2
  • 5
    • 33745217011 scopus 로고    scopus 로고
    • Crack growth behaviour of low alloy steels for pressure boundary components under transient light water reactor operating conditions
    • EU project CASTOC"
    • M. Žamboch, J. Föhl, "Crack Growth Behaviour of Low Alloy Steels for Pressure Boundary Components Under Transient Light Water Reactor Operating Conditions", EU project CASTOC", Technical Report WP3, 2003.
    • (2003) Technical Report , vol.WP3
    • Žamboch, M.1    Föhl, J.2
  • 6
    • 33745213870 scopus 로고    scopus 로고
    • Crack growth behaviour of low alloy steels for pressure boundary components under transient light water reactor operating conditions
    • EU project CASTOC"
    • A. Roth, B. Devrient, J. Föhl, "Crack Growth Behaviour of Low Alloy Steels for Pressure Boundary Components Under Transient Light Water Reactor Operating Conditions", EU project CASTOC", Technical Report WP4, 2003.
    • (2003) Technical Report , vol.WP4
    • Roth, A.1    Devrient, B.2    Föhl, J.3
  • 8
    • 33745218159 scopus 로고    scopus 로고
    • Mitteilungen aus dem VGB-arbeitskreis "SWR-chemie": Revision der VGB-richtlinie für das wasser in kernkraftwerken mit leichtwasserreaktoren (VGB-R 401 J)
    • Mitteilungen aus dem VGB-Arbeitskreis "SWR-Chemie": Revision der VGB-Richtlinie für das Wasser in Kernkraftwerken mit Leichtwasserreaktoren (VGB-R 401 J); VGB Kraftwerkstechnik 76 (1996), 238-239.
    • (1996) VGB Kraftwerkstechnik , vol.76 , pp. 238-239
  • 10
    • 30344442073 scopus 로고    scopus 로고
    • Research and service experience with environmentally assisted cracking of low-alloy steel pressure boundary components under LWR conditions
    • H. P. Seifert, S. Ritter, J. Hickling, "Research and Service Experience with Environmentally Assisted Cracking of Low-Alloy Steel Pressure Boundary Components under LWR Conditions", Power Plant Chemistry 6 (2004), pp. 111-123.
    • (2004) Power Plant Chemistry , vol.6 , pp. 111-123
    • Seifert, H.P.1    Ritter, S.2    Hickling, J.3
  • 11
    • 0344204055 scopus 로고    scopus 로고
    • Rules for in-service inspection of nuclear power plant components"
    • Appendix A, Article A-4000, "Material Properties"
    • ASME Boiler and Pressure Vessel Code, Section XI, "Rules for In-service Inspection of Nuclear Power Plant Components", Appendix A, Article A-4000, "Material Properties".
    • ASME Boiler and Pressure Vessel Code, Section XI
  • 12
    • 0031125019 scopus 로고    scopus 로고
    • Interactive effect of dynamic strain ageing with high temperature water on the crack initiation behaviour of reactor pressure vessel steels
    • ASTM STP 1298, W. A. Van Der Sluys, R. S. Piascik, and R. Zawierucha, Eds., American Society for Testing and Materials
    • Atkinson, J. D.; Zhaou, Z.-J.; Yu, J.: "Interactive Effect of Dynamic Strain Ageing with High Temperature Water on the Crack Initiation Behaviour of Reactor Pressure Vessel Steels"; in: Effects of the Environment on the Initiation of Crack Growth, ASTM STP 1298, W. A. Van Der Sluys, R. S. Piascik, and R. Zawierucha, Eds., American Society for Testing and Materials, pp. 199-215, 1997.
    • (1997) Effects of the Environment on the Initiation of Crack Growth , pp. 199-215
    • Atkinson, J.D.1    Zhaou, Z.-J.2    Yu, J.3
  • 14
    • 33745197414 scopus 로고    scopus 로고
    • Fatigue crack growth rate curves for ferritic steels in PWR water environment
    • Section XI, Division 1, May
    • Cases of ASME Boiler & Pressure Vessel Code, Case N-643; "Fatigue Crack Growth rate Curves for Ferritic Steels in PWR Water Environment", Section XI, Division 1, May 2000.
    • (2000) Cases of ASME Boiler & Pressure Vessel Code, Case N-643
  • 15
    • 33745189694 scopus 로고    scopus 로고
    • Experimental investigations concerning the possible effect of dynamic strain ageing in the environmentally assisted cracking of low alloy steels in oxygenated high temperature water
    • Stuttgart, October 09 and 10
    • A. Roth, et al., "Experimental investigations concerning the possible effect of dynamic strain ageing in the environmentally assisted cracking of low alloy steels in oxygenated high temperature water", 29. MPA Seminar on safety and reliability in energy technology, Stuttgart, October 09 and 10, 2003.
    • (2003) 29. MPA Seminar on Safety and Reliability in Energy Technology
    • Roth, A.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.