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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.
Seihiro Itoya, Masami Kato, Nobuaki Abe, Hideo Nagasaka
Nuclear Technology | Volume 77 | Number 1 | April 1987 | Pages 32-45
Technical Paper | Nuclear Safety | doi.org/10.13182/NT87-A33949
Articles are hosted by Taylor and Francis Online.
Simulation tests of a boiling water reactor (BWR) loss-of -coolant accident (LOCA) caused by a double-ended guillotine break of a recirculation pump suction line were carried out with the rig of safety assessment III (ROSA-III) test facility at the Japan Atomic Energy Research Institute. SAFER03 and TRAC-BD1 analyses with the ROSA-III test data have been performed to assess predictive capability for the large-break LOCA thermal-hydraulic response of a BWR. The analytical results indicate that SAFER03 and TRAC-BD1 predicted key phenomena very well. Furthermore, it was confirmed that SAFER03 predicted higher peak cladding surface temperature than the test data due to the conservative thermal-hydraulic model.
