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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.
S. B. Gunst, E. D. McGarry, J. J. Scoville
Nuclear Science and Engineering | Volume 7 | Number 5 | May 1960 | Pages 407-418
Technical Paper | doi.org/10.13182/NSE60-A25738
Articles are hosted by Taylor and Francis Online.
Natural uranium dioxide specimens of Shippingport PWR-l blanket-rod geometry are exposed in the Materials Testing Reactor (flux 2 × 1014 n/cm2−sec) and discharged periodically (every three weeks) for measurements in the Reactivity Measurement Facility (RMF). The time-integrated thermal and epithermal fluxes are measured during each exposure cycle, and together with the MTR Daily Power Logs, give the complete exposure history. Measurements in the RMF are used to determine an experimental value for η/η0 (η0 is the preirradiation value) which may be compared with the theoretical η/η0 calculated for the measured exposure history using appropriate neutron-interaction parameters. In the theoretical calculations, the thermal absorption cross section of stable fission products is taken to be 50 barns per fission. Although the experimental and theoretical results are derived completely independently, agreement within 1 % in η/η0 is found for the behavior following all cycles of irradiation comprising exposures from zero to 15,600 Mwd/ton.