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Conference Spotlight
2026 ANS 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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AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
B. F. Rubin, T. J. Black, W. K. Appleby, J. D. Stephen, R. F. Hilbert
Nuclear Technology | Volume 16 | Number 1 | October 1972 | Pages 89-99
Technical Paper | Reactor Materials Performance / Material | doi.org/10.13182/NT72-A31178
Articles are hosted by Taylor and Francis Online.
Experimental determinations of cladding plastic deformation in (U,Pu)O2 fuel rods, clad with annealed Type 316 stainless steel and irradiated in EBR-II, indicate that fuel-cladding mechanical interaction takes place between ∼3 and 8 at.% burnup. At higher burnups, the cladding swelling rate increases markedly resulting in no further fuel-induced plastic deformation. The maximum cladding plastic strain exhibited by several annealed Type 316 stainless-steel-clad rods was 0.4%. Cladding plastic strain was found to be independent of smeared density in the range of 83 to 91% TD.