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Probabilistic failure assessment of spent nuclear fuel cladding based on critical crack depth
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DOI：10.1016/j.net.2026.104540.png)
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Abstract
En 中文
Due to the scarcity of post-irradiation examination (PIE) data regarding the fracture properties of spent nuclear fuel, establishing statistical distributions for fracture and crack characteristics has been challenging. This study develops a probabilistic failure model for zirconium alloy cladding—demonstrated here using Westinghouse 17×17 fuel parameters as a representative example—to provide quantitative data supporting current safety regulatory guidelines. The methodology is general and can be applied to other fuel types by substituting appropriate input parameters.
Keywords:
Zirconium
Cladding
Failure rate
Fracture
Crack
Probability
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