Rigorous derivation of interfacing system LOCA frequency formulas for probabilistic safety assessment of nuclear power plants
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DOI: 10.1016/j.ress.2023.109470
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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).
- 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).
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Keywords
Interfacing system loss of coolant accident; Initiating event frequency; Probabilistic safety assessment; Nuclear power plants;All these keywords.
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