Fatigue Crack Growth Rate of Medium and Low Sulfur Ferritic Steels in Pressurized Water Reactor Primary Water Environments

[+] Author and Article Information
Ernest D. Eason, Edward E. Nelson

Modeling and Computing Services LLC, 6560 Gunpark Drive, Suite B, Boulder, Colorado 80301 USA

Graham B. Heys

H.M. Nuclear Installations Inspectorate, U.K. Health and Safety Executive, St Peters House, Balliol Road, Bootle, Merseyside, L20 3LZ, England

J. Pressure Vessel Technol 125(4), 385-392 (Nov 04, 2003) (8 pages) doi:10.1115/1.1613948 History: Received June 23, 2003; Revised June 27, 2003; Online November 04, 2003
Copyright © 2003 by ASME
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A533B plate data, S≤0.013 wt.%
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HAZ data in A508, S≤0.015 wt.%
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Weld data in A508, S≤0.015 wt.%
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A508 forging data, S≤0.013 wt.%,T<150°C
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Schematic of time domain analysis
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Short rise time data, TR≤1 s,S≤0.013 wt.%
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Histogram of A508 data, 0.004≤S≤0.015 wt.%,TR>1 s
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A508 forging data, S≤0.013 wt.%,T≥150°C




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