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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, F. D. Shum, Jun-Ichiro Otonari, Hideo Nagasaka
Nuclear Technology | Volume 80 | Number 3 | March 1988 | Pages 349-359
Technical Paper | Fission Reactor | doi.org/10.13182/NT88-A34059
Articles are hosted by Taylor and Francis Online.
The advanced boiling water reactor (ABWR) is designed to represent the next generation of boiling water reactors (BWRs), to be introduced into commercial operation in the 1990s. The response of the ABWR to loss-of-coolant accidents (LOCAs) was simulated in the full integral simulation test (FIST)-ABWR test facility. However, the emergency core cooling system structure was somewhat different from the current ABWR design. The LOCA experimental results of FIST-ABWR showed that a core was completely covered by a two-phase mixture and cooled by natural circulation without any rod heatup. The SAFER03 computer code has a newly developed evaluation model for the analysis of BWR LOCAs. SAFER03 analyses with the FIST-ABWR test data were performed to assess its ability to predict thermal-hydraulic responses for various postulated break locations in an ABWR. The analytical results indicate that SAFER03 accurately predicted pressure history, down-comer level response, and key phenomena, such as no core uncovery and no rod heatup. Consequently, it was confirmed that SAFER03 is applicable for ABWR LOCA analyses.