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TECHNICAL PAPERS

Fatigue Crack Growth Curve for Austenitic Stainless Steels in BWR Environment

[+] Author and Article Information
M. Itatani, M. Asano

Power and Industrial Systems R&D Center, Toshiba Corporation, Yokohama, Kanagawa, 230-0045, Japan

M. Kikuchi

Isogo Nuclear Engineering Center, Toshiba Corporation, Yokohama, Kanagawa, 235-0032, Japan

S. Suzuki

Power Engineering R&D Center, Tokyo Electric Power Company, Yokohama, Kanagawa, 230-8510, Japan

K. Iida

Saitama, 343-0044, Japan

J. Pressure Vessel Technol 123(2), 166-172 (Dec 19, 2000) (7 pages) doi:10.1115/1.1358841 History: Received April 17, 2000; Revised December 19, 2000
Copyright © 2001 by ASME
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References

Figures

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Effects of material, sensitization and DO on FCGR in BWR water environment (R=0.1,f=0.002 Hz)
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Effects of material, thermal aging, and prestrain on FCGR in BWR water environment (R=0.1,f=0.0167 Hz)
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Effects of material, DO, and impurities on FCGR in BWR water environment (R=0.95,f=0.08 Hz)
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Effects of loading rate on FCGR in BWR water environment (R=0.1)
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Effects of frequency on FCGR in BWR water environment (R=0.95)
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Effects of stress ratio on FCGR in BWR water environment (f=0.002 Hz)
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Determination of m1 based on the data under R=0.1,f=0.002 Hz
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Relationship between Cmax and Tr (R=0.1, 0.2, 0.5, and 0.95)
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Relationship between Cmax and Tr at n=0.5 (R=0.1, 0.5, 0.75, and 0.95)
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Dependency of FCGR on stress ratio
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Comparison between proposed curve (Tr=1 s) and ASME Code reference curve for air environment
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Comparison between proposed curve and experimental data (0.008≦f≦5 Hz)
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Comparison between proposed curve and experimental data (R=0.6–0.75)
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Comparison between proposed curve and experimental data (R=0.2)

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