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Volumn 235, Issue 17-19, 2005, Pages 1919-1937

Leak before Break application for Primary Coolant Loop and Surge Line of VVER-1000/320 Plant: TACIS Project R2.09/96

Author keywords

[No Author keywords available]

Indexed keywords

CLADDING (COATING); COOLANTS; FRACTURE; PIPING SYSTEMS; PROJECT MANAGEMENT; STAINLESS STEEL; TENSILE PROPERTIES;

EID: 23744434647     PISSN: 00295493     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.nucengdes.2005.06.002     Document Type: Article
Times cited : (6)

References (15)
  • 2
    • 33644567524 scopus 로고    scopus 로고
    • Fracture 1.0 computer code: Flaw stability analysis, crack opening area calculation
    • Fracture 1.0 Computer Code: Flaw Stability Analysis, Crack Opening Area Calculation. ENES Report, 1999.
    • (1999) ENES Report
  • 3
    • 33644581842 scopus 로고    scopus 로고
    • M-LBB-01-99, RD 95 10547-99 (MAE), Moscow (in Russian)
    • LBB Application Guide for NPP pipelines, M-LBB-01-99, RD 95 10547-99 (MAE), Moscow, 1999 (in Russian).
    • (1999) LBB Application Guide for NPP Pipelines
  • 4
    • 33644573667 scopus 로고
    • NUREG-1061 US Nuclear Regulatory Commission
    • NUREG-1061, vol. 3, US Nuclear Regulatory Commission, Evaluation of Potential for Pipe Breaks, 1984.
    • (1984) Evaluation of Potential for Pipe Breaks , vol.3
  • 12
    • 0242284047 scopus 로고
    • 3.6.3" Leak Before Break Evaluation Procedures", Washington, DC
    • US NRC Standard Review Plan, 3.6.3" Leak Before Break Evaluation Procedures", Washington, DC, 1986.
    • (1986) US NRC Standard Review Plan
  • 14
    • 0025632635 scopus 로고
    • Recent Results of Fracture Experiments on Carbon Steel
    • G. Wilkowsky Recent Results of Fracture Experiments on Carbon Steel Int. J. Pres. Ves. Piping 43 1990
    • (1990) Int. J. Pres. Ves. Piping , vol.43
    • Wilkowsky, G.1
  • 15
    • 33644562974 scopus 로고    scopus 로고
    • Application of the LBB concept to nuclear power plants with WWER 440 and WWER 1000
    • US NRC, NUREG/CP-0155
    • J. Zdarek Application of the LBB concept to nuclear power plants with WWER 440 and WWER 1000 Proceedings of the Seminar on LBB in Reactor Piping and Vessels US NRC, NUREG/CP-0155 1997 101 125
    • (1997) Proceedings of the Seminar on LBB in Reactor Piping and Vessels , pp. 101-125
    • Zdarek, J.1


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.