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Quality is key: Investing in advanced nuclear research for tomorrow’s grid
As the energy sector faces mounting pressure to grow at an unprecedented pace while maintaining reliability and affordability, nuclear technology remains an essential component of the long-term solution. Southern Company stands out among U.S. utilities for its proactive role in shaping these next-generation systems—not just as a future customer, but as a hands-on innovator.
Hsoung-Wei Chou, Chin-Cheng Huang, Pin-Chiun Huang, Yuh-Ming Ferng
Nuclear Technology | Volume 206 | Number 12 | December 2020 | Pages 1919-1931
Technical Paper | doi.org/10.1080/00295450.2020.1724729
Articles are hosted by Taylor and Francis Online.
In recent years, the compound beyond-design-basis accident (BDBA), which combines earthquake, tsunami, or some other severe events to impact a nuclear power plant (NPP), has received more attention. After the Fukushima nuclear disaster, the licensee of NPPs in Taiwan established the ultimate response guideline (URG) that instructs operators to perform reactor depressurization, low-pressure water injection, and containment venting to prevent core meltdown and hydrogen explosion once long-term loss-of-power and water-supply events occur. In this paper, we employed the probabilistic fracture mechanics (PFM) method to evaluate the structural integrity of boiling water reactor (BWR) pressure vessels under URG operation. At first, models of the beltline shell welds for BWR vessels associated with the Pressure Vessel Research Users Facility-Exponential flaw distribution were built for the PFM Fracture Analysis of Vessels–Oak Ridge (FAVOR) code. Then, the thermal-hydraulic data of URG transients for Taiwan domestic BWRs were imposed as the loading conditions. The analysis results demonstrate that performing URG operation will not cause significant fracture probability even at extreme embrittlement conditions. If long-term station blackout occurs due to a compound BDBA, the URG procedures can prevent core damage and hydrogen explosion, while maintaining the structural integrity of the reactor pressure vessels.