Effect of elastic follow-up on creep-fatigue life of 316FR stainless steel

American Society of Mechanical Engineers, Pressure Vessels and Piping Division (Publication) PVP

Volumn 391, Issue , 1999, Pages 151-157

  Takahashi, Yukio ^a   Date, Shingo ^b   Kaguchi, Hitoshi ^b  

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

^b MITSUBISHI HEAVY INDUSTRIES LTD   (Japan)

Author keywords

[No Author keywords available]

Indexed keywords

BREEDER REACTORS; COMPUTATIONAL METHODS; CREEP TESTING; ELASTICITY; FAILURE ANALYSIS; FAST REACTORS; FATIGUE TESTING; LOAD TESTING; MATHEMATICAL MODELS; SERVICE LIFE; STEEL TESTING;

CREEP-FATIGUE TESTS; ELASTIC FOLLOW-UP; FAST BREEDER REACTORS; LIFE PREDICTION METHOD; STAINLESS STEEL 316;

STAINLESS STEEL;

EID: 0033315333     PISSN: 0277027X     EISSN: None     Source Type: Conference Proceeding    
DOI: None     Document Type: Conference Paper

References (10)

1. American Society for Mechanical Engineers, 1995, Boiler and Pressure Vessel Code, Section III, Division 1 - Subsection NH.
2. Association francaise pour les regles de conception et de construction des materials des chaudieres electro-nucleaires (afcen), 1985, "Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, RCC-MR".
3. Brinkman, C. R., 1985, "High-Temperature Time-Dependent Fatigue Behaviour of Several Engineering Structural Alloys", International Metals Reviews, Vol. 30, No.5, pp. 235-258.
4. Campbell, R. D., 1971, "Creep/Fatigue Interaction Correlation for 304 Stainless Steel Subjected to Strain-Controlled Cycling with Hold Times at Peak Strain", ASME, Journal of Engineering for Industry, pp. 887-892.
5. Clayton, A. M., 1988, "Creep-Fatigue Assessment Procedures for Fast Reactors", Recent Advances in Design Procedures for High Temperature Plant, Institution of Mechanical Engineers, pp. 49-54.
6. Hales, R., 1983, "A Method of Creep Damage Summation Based on Accumulated Strain for the Assessment of Creep-Fatigue Endurance", Fatigue of Engineering Materials and Structures, Vol.6, No.2, pp. 121-135.
7. Power Reactor and Nuclear Fuel Development Corporation, 1984, "High Temperature Structural Design Guide for Fast Prototype Reactor", PNC N241 84-08(1) (in Japanese).
8. Priest, R. H. and Ellison, E. G., 1980, "A Combined Deformation Map - Ductility Exhaustion Approach to Creep-Fatigue Analysis", Material Science and Engineering, Vol. 49, p.7.
9. Takahashi, Y., 1998a, "Evaluation of Creep-Fatigue Life Prediction Methods for Low-Carbon Nitrogen-added 316 Stainless Steel", ASME Journal of Engineering Materials and Technology, Vol.120, pp.119-125.
10. Takahashi, Y., 1998b, "Advancement of High-Temperature Structural Design Method for Fast Reactor Components Part I : Creep-Fatigue Damage Evaluation Method for 316FR", ASME PVP-Vol. 5, Book No. H01146, pp.159-166.