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Journal Articles

Uncertainty analysis of dynamic PRA using nested Monte Carlo simulations and multi-fidelity models

Zheng, X.; Tamaki, Hitoshi; Takahara, Shogo; Sugiyama, Tomoyuki; Maruyama, Yu

Proceedings of Probabilistic Safety Assessment and Management (PSAM16) (Internet), 10 Pages, 2022/09

Journal Articles

Dynamic probabilistic risk assessment of nuclear power plants using multi-fidelity simulations

Zheng, X.; Tamaki, Hitoshi; Sugiyama, Tomoyuki; Maruyama, Yu

Reliability Engineering & System Safety, 223, p.108503_1 - 108503_12, 2022/07

 Times Cited Count:17 Percentile:91.72(Engineering, Industrial)

Oral presentation

Development of dynamic PRA using multi-fidelity models

Zheng, X.; Tamaki, Hitoshi; Sugiyama, Tomoyuki; Maruyama, Yu

no journal, , 

no abstracts in English

Oral presentation

Study on the applicability of dynamic level 2 PRA to estimating large early release frequency

Zheng, X.; Takahara, Shogo; Tamaki, Hitoshi; Sugiyama, Tomoyuki; Maruyama, Yu

no journal, , 

no abstracts in English

Oral presentation

Implementation of physics-of-failure modeling techniques toward more realistic dynamic PRA

Zheng, X.; Tamaki, Hitoshi; Shibamoto, Yasuteru; Takada, Tsuyoshi

no journal, , 

JAEA is constructing a dynamic probabilistic risk assessment (PRA) approach which integrates deterministic accident analysis and probabilistic reliability analysis, and developing an associated computational tool, RAPID. Taking the estimation of failure probability of machines as an example, this paper identifies latent sources of epistemic uncertainties in PRA. To reduce such epistemic uncertainties, authors have proposed to apply probabilistic physics-of-failure by dynamically modeling the interaction between operational conditions and failure probabilities of machines. Moreover, authors have implemented automatic coupling techniques between simulation codes in RAPID.

Oral presentation

Cutting edge of application of AI technology to PRA, 3; Advancement of approaches to dynamic PRA and uncertainty quantification using machine learning

Zheng, X.; Tamaki, Hitoshi; Shibamoto, Yasuteru; Maruyama, Yu

no journal, , 

The nuclear industry is expressing a growing interest in the research and use of artificial intelligence and machine learning (AI/ML) technology to improve plant operational performance and reduce the risks associated with nuclear power generation. JAEA is applying the AI/ML technology to advancing researches on severe accidents and probabilistic risk assessment (PRA). To efficiently perform dynamic PRA and uncertainty quantification of source terms, both simulation-based, we are introducing surrogate models trained via machine learning to estimate core damage frequency (conditional core damage probability), to obtain information about the probability distribution of source terms and importance ranking of parameters. AI/ML can be expected to efficiently provide risk and uncertainty information to make rational decisions for the continuous improvement of nuclear safety.

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