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2026 Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Modernizing I&C for operations and maintenance, one phase at a time
The two reactors at Dominion Energy’s Surry plant are among the oldest in the U.S. nuclear fleet. Yet when the plant celebrated its 50th anniversary in 2023, staff could raise a toast to the future. Surry was one of the first plants to file a subsequent license renewal (SLR) application, and in May 2021, it became official: the plant was licensed to operate for a full 80 years, extending its reactors’ lifespans into 2052 and 2053.
Lee A. James
Nuclear Technology | Volume 74 | Number 1 | July 1986 | Pages 84-92
Technical Paper | Material | doi.org/10.13182/NT86-A33821
Articles are hosted by Taylor and Francis Online.
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.
