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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.
Adam Rau, James Turso (Penn State)
Proceedings | Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technolgies (NPIC&HMIT 2019) | Orlando, FL, February 9-14, 2019 | Pages 1352-1360
Maintaining system stability is an important task for operators of nuclear reactors. Automatic control can be a valuable tool in achieving this, however many modern control methods require a model of the system. These models may not account for changes in system parameters resulting from continued use or different operating points. Robust control techniques can account for such uncertainties, guaranteeing stability provided that plant parameters and dynamics remain within specified uncertainty bounds. The present work applies robust control methods to design a controller for the Penn State Breazeale Reactor (PSBR). The impact of wear on the control rod drive mechanism and changes resulting from different reactor power set points are considered. A Simulink model of the PSBR from [1] was linearized and simplified for the purpose of controller design. The model uses the normalized point-kinetics equations and core-averaged thermal-hydraulics. H? control synthesis methods were used to accommodate changes in power level and wear in the control rod drive mechanisms. System stability was verified on a Simulink model, and controller performance was compared to a proportional controller.