Pre and postirradiation fatigue crack growth rates in A302-B, A533-B, and A543 steel plate and in two A543 welds (submerged arc and electroslag) were determined at 550 deg F (288 deg C) in air. The fracture mechanics approach was used to analyze the experimental data. Neutron irradiation at 585 deg F (307 deg C) to 2.5 × 1019 n/cm2, > 1 MeV produced no significant effect on resistance to crack growth in A302-B steel and caused only a slight decrease in crack growth resistance of A533-B and A543 steels. Also, the resistance to crack growth of the submerged arc weld was unaffected by the irradiation, but that of the electroslag weld was substantially improved. The crack growth rate versus stress intensity factor range curve for the A302-B steel represents an upper bound for the pre and postirradiation data for the steels and welds of this study.
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October 1974
Research Papers
Fatigue Crack Growth Resistance of Several Neutron Irradiated Pressure Vessel Steels and Welds
P. Shahinian,
P. Shahinian
Metallurgy Division, Naval Research Laboratory, Washington, D. C.
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H. E. Watson,
H. E. Watson
Metallurgy Division, Naval Research Laboratory, Washington, D. C.
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J. R. Hawthorne
J. R. Hawthorne
Metallurgy Division, Naval Research Laboratory, Washington, D. C.
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P. Shahinian
Metallurgy Division, Naval Research Laboratory, Washington, D. C.
H. E. Watson
Metallurgy Division, Naval Research Laboratory, Washington, D. C.
J. R. Hawthorne
Metallurgy Division, Naval Research Laboratory, Washington, D. C.
J. Eng. Mater. Technol. Oct 1974, 96(4): 242-248 (7 pages)
Published Online: October 1, 1974
Article history
Received:
January 25, 1974
Revised:
March 5, 1974
Online:
August 17, 2010
Citation
Shahinian, P., Watson, H. E., and Hawthorne, J. R. (October 1, 1974). "Fatigue Crack Growth Resistance of Several Neutron Irradiated Pressure Vessel Steels and Welds." ASME. J. Eng. Mater. Technol. October 1974; 96(4): 242–248. https://doi.org/10.1115/1.3443237
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