Abstract
Type 316FR stainless steel has been developed as a candidate material for fast breeder reactors. To ensure the structural integrity at high temperature of the reactor components including the reactor vessel, long-term data and an analysis method are investigated for 316FR steel to evaluate time-dependent low-cycle fatigue behavior. The present study reports the dependence from 550 to 600°C. Data are analyzed using a parameter method previously proposed by the authors. It is shown that the method effectively predicts fatigue life even at a very low strain rate of 10−6/s.
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