軽水炉機器低合金鋼および炭素鋼の疲労き裂進展データベースの構築と統計解析・評価

概要

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A data base of the fatigue crack growth for nuclear component ferritic steels was constructed. Data collected are of the low alloy steels (A533B-1, A508-2, A508-3) and a carbon steel (STS42) tested in air from room temperature up to 371℃. 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×l0^<-9>{(1 + 0.30R)(E_0/E)^<0.51>ΔK}^<3.02> (da/dN : mm/cycle, ΔK : MPa√<m>), where da/dN is the fatigue crack growth rate, R is the stress ratio, E_0 is the Young's modulus at RT, E is the Young's modulus at the temperature concerned and AK is the stress intensity factor range. This equation proved better applicability than the one proposed in ASME.
一般社団法人日本機械学会の論文
1989-06-25