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Experimental Evaluation of Fatigue Threshold for SA-508 Reactor Vessel Steel  

Rhee, Hwan-Woo (경남대학교 기계공학부)
Publication Information
Journal of the Korean Society of Manufacturing Process Engineers / v.11, no.4, 2012 , pp. 160-167 More about this Journal
Abstract
This paper is concerned with a particular fracture mechanics parameter ${\Delta}K_{th}$, known as the 'threshold stress intensity range', or 'fatigue threshold'. This threshold ${\Delta}K_{th}$ constitutes, as it were, a hinge between the notion of crack initiation and the notion of crack growth. It has often been thought that, like the endurance limit, it could be an intrinsic criterion of the material. The study was conducted on a SA-508 pressure vessel steel used in the nuclear power industry. This material exhibits a typical threshold effect in the range of the crack growth rates which were determined; that is, below approximately $da/dN=10^{-6}mm/cycle$, the slope of the da./dN versus ${\Delta}K$ curve is almost vertical. The value of ${\Delta}K_{th}$ was determined at a growth rate of $10^{-7}$ mm/cycle according to the ASTM Standard for threshold testing. The fatigue threshold values are in the range 21 $kg/mm^{3/2}$ to 12 $kg/mm^{3/2}$ depending on the stress ratio effect.
Keywords
Reactor Vessel Steel; Fatigue Threshold; Stress Intensity Factor; Load Shedding Method; Stress Ratio;
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