Demonstration of Structural Integrity of Boiling Water Reactor Pressure Vessels Under Ultimate Response Guideline Operation

• Published in: Nuclear technology Vol. 206; no. 12; pp. 1919 - 1931
• Main Authors: Chou, Hsoung-Wei, Huang, Chin-Cheng, Huang, Pin-Chiun, Ferng, Yuh-Ming
• Format: Journal Article
• Language: English
• Published: La Grange Park Taylor & Francis 01.12.2020; American Nuclear Society
• Subjects: boiling water reactor; Probabilistic fracture mechanics; ultimate response guideline; warm-prestress effects
• ISSN: 0029-5450; 1943-7471
• DOI: 10.1080/00295450.2020.1724729

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.