Fragility analysis and probabilistic performance evaluation of nuclear containment structure subjected to internal pressure
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DOI: 10.1016/j.ress.2020.107400
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References listed on IDEAS
- Kwag, Shinyoung & Gupta, Abhinav & Dinh, Nam, 2018. "Probabilistic risk assessment based model validation method using Bayesian network," Reliability Engineering and System Safety, Elsevier, vol. 169(C), pages 380-393.
- Seyed Mojtaba Hoseyni & Seyed Mohsen Hoseyni & Faramarz Yousefpour & Kaveh Karimi, 2017. "Probabilistic analysis of containment structural performance in severe accidents," International Journal of System Assurance Engineering and Management, Springer;The Society for Reliability, Engineering Quality and Operations Management (SREQOM),India, and Division of Operation and Maintenance, Lulea University of Technology, Sweden, vol. 8(3), pages 625-634, September.
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Cited by:
- Li, Xinbo & Gong, Jinxin, 2024. "Probabilistic evaluation of the leak-tightness function of the nuclear containment structure subjected to internal pressure," Reliability Engineering and System Safety, Elsevier, vol. 241(C).
- Bhuyan, Kasturi & Sharma, Hrishikesh, 2024. "Probabilistic capacity models and fragility estimate for NRC and UHSC panels subjected to contact blast," Reliability Engineering and System Safety, Elsevier, vol. 242(C).
- Dhulipala, Somayajulu L.N. & Shields, Michael D. & Chakroborty, Promit & Jiang, Wen & Spencer, Benjamin W. & Hales, Jason D. & Labouré, Vincent M. & Prince, Zachary M. & Bolisetti, Chandrakanth & Che, 2022. "Reliability estimation of an advanced nuclear fuel using coupled active learning, multifidelity modeling, and subset simulation," Reliability Engineering and System Safety, Elsevier, vol. 226(C).
- Zheng, Zhi & Tian, Aonan & Pan, Xiaolan & Ji, Duofa & Wang, Yong, 2024. "The damage-based fragility analysis and probabilistic safety assessment of containment under internal pressure," Reliability Engineering and System Safety, Elsevier, vol. 241(C).
- Liu, Jiaxin & Yu, Deping & Yang, Taibo & Liu, Caixue & Wang, Guangjin & Liu, Xiaoming, 2023. "Discovering the causes for the change of the vibration characteristics of the core support barrel in PWR nuclear power plants: A combined investigation based on ex-core neutron noise analysis and nume," Reliability Engineering and System Safety, Elsevier, vol. 234(C).
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Keywords
Nuclear containment structure; Fragility analysis; Probabilistic performance evaluation; Bootstrap method; Cumulative failure probability; Probabilistic safety margin;All these keywords.
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