Fatigue Crack Growth Characteristics of A533 Grade B Class I Plate in an Environment of High-Temperature Primary Grade Nuclear Reactor Water

[+] Author and Article Information
T. R. Mager

Mat. Engrg., Westinghouse Nuclear Europe, Brussels, Belgium

D. M. Moon

Power Generation Materials Research, Pittsburgh, Pa.

J. D. Landes

Westinghouse Research Laboratories, Pittsburgh, Pa.

J. Pressure Vessel Technol 99(2), 238-247 (May 01, 1977) (10 pages) doi:10.1115/1.3454526 History: Received December 05, 1975; Online October 25, 2010


Fatigue crack growth rate tests conducted in primary grade reactor coolant at 550°F (288°C) on A533 Grade B Class 1 steel (HSST Plate 02) showed an increase in growth rates at a frequency of 1 cpm over previous results obtained at frequencies of 60 cpm and higher. This increase, the general character of the crack growth rate versus the ΔK curve, and the results from fractographic studies, all indicated that stress corrosion cracking might have occurred for this material and environment. However, a specimen loaded statically in a PWR environment showed no static load crack growth.

Copyright © 1977 by ASME
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