Fatigue crack propagation under cyclic thermal stress

Materials at High Temperatures

Volumn 15, Issue 3-4, 1998, Pages 285-290

  Kaguchi, H ^a   Koto, H ^a   Date, S ^a   Takahashi, Y ^b  

^a MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

^b CENTRAL RESEARCH INSTITUTE OF ELECTRIC POWER INDUSTRY   (Japan)

Author keywords

316FR; Fast reactor; Fracture mechanics; J integral; Thermal stress

Indexed keywords

CRACK PROPAGATION; ELASTOPLASTICITY; FAST REACTORS; FATIGUE TESTING; FRACTURE MECHANICS; INDUCTION HEATING; NUMERICAL ANALYSIS; STEEL TESTING; STRESS ANALYSIS; TEMPERATURE DISTRIBUTION; THERMAL CYCLING; THERMAL STRESS;

STAINLESS STEEL 316FR;

STAINLESS STEEL;

EID: 0032314929     PISSN: 09603409     EISSN: None     Source Type: Journal    
DOI: 10.1080/09603409.1998.11689613     Document Type: Article

References (5)

1. Nakazawa, T. et al. Effects of Carbon, Nitrogen and Molybdenum of Creep Properties of Type 316 Stainless Steel. Proceedings of 6th International Conference on Pressure Vessel Technology, Vol. 2, Beijing (1988).
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3. Kaguchi, H. et al. Fundamental Research on Creep Fatigue Fracture of Type 316 Stainless Steel for Fast Breeder Reactors. SMiRT 11 Transactions Vol. E. Tokyo, Japan, E05/2 (1991).
4. Kumar, V. et al. Estimation Techniques for the Prediction of Elastic-Plastic Fracture of Structural Components of Nuclear Systems. RP-1237-1, GE/EPRI (1982).
5. Ainsworth, R. A. et al. Defect Assessment at Elevated Temperature. Journal of Pressure Vessel Technology, 105, 263-268 (1983).