日本機械学会論文集 A編
Online ISSN : 1884-8338
Print ISSN : 0387-5008
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
小林 英男中村 春夫笠井 憲一斉藤 正博船田 立夫柴田 勝之飯田 國廣
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1989 年 55 巻 514 号 p. 1255-1263

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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°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×l0-9{(1 + 0.30R)(E0/E)0.51ΔK}3.02 (da/dN : mm/cycle, ΔK : MPa√(m)), where da/dN is the fatigue crack growth rate, R is the stress ratio, E0 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.

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