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The Effect of Fast-Neutron Irradiation on the Fatigue-Crack Growth Behavior of Several Austenitic Stainless Steels and Weldments

Lee A. James

Nuclear Technology

Volume 74 / Number 1 / July 1986 / Pages 84-92


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Fatigue-crack growth specimens from a number of austenitic stainless steels and weldments [annealed Types 304 and 316, 20% cold-worked Type 316, SA-351 Grade CF8, Type 304/308 shielded-metal-arc (SMA) weldments, and Type 316/IN-82/IN-718 gastungsten-arc weldments] were irradiated in Experimental Breeder Reactor-II. Postirradiation crack-growth testing showed little or no effect of irradiation on the crack growth behavior of annealed Type 304, coldworked Type 316, and Type 304/308 SMA weldments. On the other hand, irradiation produced a minor reduction in crack growth rates in annealed Type 316 and minor increases in crack growth rates in SA-351 Grade CF8 castings and Type 316/IN-82/IN-718 GTA weldments over certain ranges of ΔK.

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