Further Evaluation of Creep-Fatigue Life Prediction Methods for Low-Carbon Nitrogen-Added 316 Stainless Steel

Author:

Takahashi Y.1

Affiliation:

1. Materials Science Department, Central Research Institute of Electric Power Industry, 2-11-1 Iwato-kita, Komae-shi, Tokyo 201-8511, Japan

Abstract

Low-carbon, medium-nitrogen 316 stainless steel is a principal candidate for a main structural material of a demonstration fast breeder reactor plant in Japan. A number of long-term creep tests and creep-fatigue tests have been conducted for four products of this steel. Two representative creep-fatigue life prediction methods, i.e., time fraction rule and ductility exhaustion method were applied. Total stress relaxation behavior was simulated well by an addition of a viscous strain term to the conventional (primary plus secondary) creep strain, but only the letter was assumed to contribute to creep damage in the ductility exhaustion method. The present ductility exhaustion approach was found to have very good accuracy in creep-fatigue life prediction for all materials tested, while the time fraction rule tended to overpredict failure life as large as a factor of 30. Discussion was made on the reason for this notable difference.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference18 articles.

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2. afcen, 1985, “Design and Construction Rules for Mechanical Components of FBR Nuclear Islands, RCC-MR,” Association francaise pour les regles de conception et de construction des materials des chaudieres electro-nucleaires.

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.

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