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Volumn 92, Issue , 2012, Pages 1-10

Proof of fatigue strength of nuclear components part II: Numerical fatigue analysis for transient stratification loading considering environmental effects

Author keywords

Fatigue assessment; LWR environment; Numerical evaluation scheme

Indexed keywords

CODES AND STANDARDS; CORRECTION FACTORS; CYCLIC STRESS; DESIGN AND OPERATIONS; DESIGN CURVES; ENVIRONMENTAL FATIGUE; FATIGUE ANALYSIS; FATIGUE ASSESSMENTS; FATIGUE STRENGTH; GEOMETRIC COMPLEXITY; IN-SERVICE MONITORING; LIGHT WATER; LWR ENVIRONMENT; NEW DESIGN; NUCLEAR COMPONENTS; NUMERICAL EVALUATIONS; STRUCTURAL COMPONENT; THERMAL LOADINGS;

EID: 84858282494     PISSN: 03080161     EISSN: None     Source Type: Journal    
DOI: 10.1016/j.ijpvp.2012.01.005     Document Type: Review
Times cited : (7)

References (26)
  • 2
    • 0003693090 scopus 로고    scopus 로고
    • French design and construction Rules for mechanical components of PWR nuclear Islands (RCC-M)
    • AFCEN - Association Française pour la construction des Ensembles Nucléaires, Paris.
    • French design and construction Rules for mechanical components of PWR nuclear Islands (RCC-M). AFCEN - Association Française pour la construction des Ensembles Nucléaires, Paris.
  • 3
    • 84870971480 scopus 로고    scopus 로고
    • Safety standards of the nuclear safety standards Commission (KTA)
    • KTA Rules 3201 and 3211, Carl Heymanns Verlag KG, Cologne, latest edition.
    • Safety standards of the nuclear safety standards Commission (KTA). KTA Rules 3201 and 3211, Carl Heymanns Verlag KG, Cologne, latest edition.
  • 5
    • 85006346169 scopus 로고
    • Design of pressure vessels for low-cycle fatigue
    • Langer B.F. Design of pressure vessels for low-cycle fatigue. Journal of Basic Engineering September 1962, 84(3):389-402.
    • (1962) Journal of Basic Engineering , vol.84 , Issue.3 , pp. 389-402
    • Langer, B.F.1
  • 8
    • 84858278300 scopus 로고    scopus 로고
    • Fatigue strength reduction and stress concentration factors for welds in pressure vessels and piping - Report No. 1: Interpretive Review of Weld Fatigue-Strength-Reduction and Stress-Concentration Factors, by C.E. Jaske; Report No. 2: Fatigue-Strength-Reduction Factors for Welds Based on NDE, by J.L. Hechemer and E.J. Kuhn
    • Fatigue strength reduction and stress concentration factors for welds in pressure vessels and piping - Report No. 1: Interpretive Review of Weld Fatigue-Strength-Reduction and Stress-Concentration Factors, by C.E. Jaske; Report No. 2: Fatigue-Strength-Reduction Factors for Welds Based on NDE, by J.L. Hechemer and E.J. Kuhn. Welding Research Council Bulletin, WRC June 1998, 432.
    • (1998) Welding Research Council Bulletin, WRC , vol.432
  • 12
    • 84858297618 scopus 로고    scopus 로고
    • 3rd Intern. Conference on Fatigue of Reactor Components, Seville, Spain
    • Higuchi M. Japanese program Overview October 3-6, 2004, 3rd Intern. Conference on Fatigue of Reactor Components, Seville, Spain.
    • (2004) Japanese program Overview
    • Higuchi, M.1
  • 16
    • 0021376779 scopus 로고
    • Thermal stratification in Steam Generator Feedwater Lines
    • Braschel R., Miksch M., Schücktanz G. Thermal stratification in Steam Generator Feedwater Lines. ASME PVP February 1984, 106:78-85.
    • (1984) ASME PVP , vol.106 , pp. 78-85
    • Braschel, R.1    Miksch, M.2    Schücktanz, G.3
  • 17
    • 0020496208 scopus 로고
    • Loading conditions in horizontal Feedwater pipes of LWR's influenced by thermal shock and thermal stratification effects
    • Miksch M., Lenz E., Löhberg R. Loading conditions in horizontal Feedwater pipes of LWR's influenced by thermal shock and thermal stratification effects. Nuclear Engineering and Design 1985, 84:179-187.
    • (1985) Nuclear Engineering and Design , vol.84 , pp. 179-187
    • Miksch, M.1    Lenz, E.2    Löhberg, R.3
  • 20
    • 84858297091 scopus 로고    scopus 로고
    • ASTM E-1049 standard Practices for cycle counting in fatigue analysis.
    • ASTM E-1049 standard Practices for cycle counting in fatigue analysis.
  • 21
    • 84858292365 scopus 로고    scopus 로고
    • Proof fatigue strength of nuclear components - part I: fatigue testing of ferritic and austenitic nuclear materials, to be published
    • Roos E, Herter KH, Schuler X, Weißenberg T. Proof fatigue strength of nuclear components - part I: fatigue testing of ferritic and austenitic nuclear materials, to be published.
    • Roos, E.1    Herter, K.H.2    Schuler, X.3    Weißenberg, T.4
  • 22
    • 84858278563 scopus 로고    scopus 로고
    • Code Case N-761, Fatigue design curves for light water reactor (LWR) environment, cases of ASME Boiler and pressure vessel code.
    • Code Case N-761, Fatigue design curves for light water reactor (LWR) environment, cases of ASME Boiler and pressure vessel code.


* 이 정보는 Elsevier사의 SCOPUS DB에서 KISTI가 분석하여 추출한 것입니다.