ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
Explore the many uses for nuclear science and its impact on energy, the environment, healthcare, food, and more.
Explore membership for yourself or for your organization.
Conference Spotlight
2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
Latest Magazine Issues
Mar 2026
Jan 2026
Latest Journal Issues
Nuclear Science and Engineering
April 2026
Nuclear Technology
February 2026
Fusion Science and Technology
Latest News
Swiss nuclear power and the case for long-term operation
Designed for 40 years but built to last far longer, Switzerland’s nuclear power plants have all entered long-term operation. Yet age alone says little about safety or performance. Through continuous upgrades, strict regulatory oversight, and extensive aging management, the country’s reactors are being prepared for decades of continued operation, in line with international practice.
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.