Probabilistic Approach for Best Estimate of Fuel Rod Fracture During Loss-of-Coolant Accident

Nuclear power plant risk assessments rely on conservative deterministic criteria for core-damage determination despite significant advancements in plant response and system analyses. This study proposes a probabilistic approach to determine fuel rod fracture during loss-of-coolant accidents (LOCAs) in light-water reactors, addressing the need for more rational and realistic assessments. The methodology integrates a fuel rod fracture probability estimation model with best-estimate-plus-uncertainty analysis of plant response, utilizing the stress–strength model and Monte Carlo simulations. Both stress and strength distributions are estimated through Bayesian statistical modeling, with numerical integration techniques implemented to enhance accuracy for low-frequency events. The application of this approach to a virtual dataset demonstrated that while conventional deterministic methods indicated definitive rod fracture, our probabilistic analysis revealed a more realistic fracture probability of 15.1%. This significant finding highlights the potential reduction in assessment conservatism. The proposed methodology enables a transition from conservative binary evaluations to more realistic probabilistic assessments of core damage, providing more accurate risk insights for decision-making.

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Publication Details

Journal
Journal of Nuclear Engineering
Published
2025-02-28
DOI
https://doi.org/10.3390/jne6010006
Primary Topic
Nuclear Materials and Properties
Type
article
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article

Probabilistic Approach for Best Estimate of Fuel Rod Fracture During Loss-of-Coolant Accident

Takashi Takata, Hiroki Tanaka, Takafumi Narukawa
Journal of Nuclear Engineering
Nuclear Materials and Properties
article

Probabilistic Approach for Best Estimate of Fuel Rod Fracture During Loss-of-Coolant Accident

Takashi Takata, Hiroki Tanaka, Takafumi Narukawa
article en

Abstract

Nuclear power plant risk assessments rely on conservative deterministic criteria for core-damage determination despite significant advancements in plant response and system analyses. This study proposes a probabilistic approach to determine fuel rod fracture during loss-of-coolant accidents (LOCAs) in light-water reactors, addressing the need for more rational and realistic assessments. The methodology integrates a fuel rod fracture probability estimation model with best-estimate-plus-uncertainty analysis of plant response, utilizing the stress–strength model and Monte Carlo simulations. Both stress and strength distributions are estimated through Bayesian statistical modeling, with numerical integration techniques implemented to enhance accuracy for low-frequency events. The application of this approach to a virtual dataset demonstrated that while conventional deterministic methods indicated definitive rod fracture, our probabilistic analysis revealed a more realistic fracture probability of 15.1%. This significant finding highlights the potential reduction in assessment conservatism. The proposed methodology enables a transition from conservative binary evaluations to more realistic probabilistic assessments of core damage, providing more accurate risk insights for decision-making.

Journal of Nuclear EngineeringVol. 6(1)
The University of Tokyo (JP)
Openalex Percentile: Top 97%
Nuclear Materials and Properties
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