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2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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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.
R. S. May, J. M. Sorensen, R. E. Engel
Nuclear Science and Engineering | Volume 103 | Number 1 | September 1989 | Pages 81-93
Technical Paper | doi.org/10.13182/NSE89-A23662
Articles are hosted by Taylor and Francis Online.
Plant transient calculations for reactor accidents and operational transient events must be performed and evaluated despite uncertainties in input data, empirical correlations, modeling assumptions, and evaluation criteria. The use of best-estimate analysis in conjunction with systematic evaluation of uncertainties provides an alternative to bounding analyses that may introduce unnecessarily large conservatisms. A methodology has been developed that combines established techniques for statistical analysis to deal with a general class of problems having uncertainties both in the evaluation criterion and the modeling parameters. Response surface and Monte Carlo sampling methods are used to determine the probability density function of the key output variable. This function is in turn combined with a probabilistic form of the evaluation criterion to estimate the probability that the criterion may be violated. The methodology is applied to an evaluation of the likelihood that high-pressure safety valves would be challenged by increasing pressure transient events in a boiling water reactor. Plant transient results are obtained from RETRAN-02 calculations, and safety valve characteristics are obtained from test data.