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2025 ANS Winter Conference & Expo
November 9–12, 2025
Washington, DC|Washington Hilton
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University of Nebraska–Lincoln: Home of ANS’s newest student section
Following official confirmation in June at the American Nuclear Society’s 2025 Annual Conference, the University of Nebraska–Lincoln has kicked off its first year as the newest ANS student section.
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.