Abstract
A database of the fatique-crack growth for nuclear-component ferritic steels was constructed. Data collected are for the low-alloy steels (A533B-1, A508-2, A508-3) and a carbon steel (STS42), tested in air from room temperature up to 371°C. Characterization of the fatigue-crack-growth data and improvement of the conventional design curve were attempted. A proposed design curve is given as follows: da/ dN = 3·57 × 10 −9 [(1 + 0·30R)(E 0/E) 0·51 ΔK] 3·02 ( da/ dN:mm/cycle, ΔK:MPa√m) where d a/d N is the fatigue-crack-growth rate, R is the stress ratio, E 0 is the Young's modulus at room temperature, E is the Young's modulus at the temperature concerned, and ΔK is the stress-intensity-factor range. This equation proved more applicable than the one proposed for the revision of Section XI of the ASME Boiler and Pressure Vessel Code.
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