2023 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 403-1 Risk Assessment Technology, Application of Risk Information

[2C07-09] PRA Method

Tue. Mar 14, 2023 2:45 PM - 3:35 PM Room C (11 Bildg.2F 1106)

Chair:Hiroshi Ujita(AdvanceSoft)

3:00 PM - 3:15 PM

[2C08] Improvement of prediction accuracy of the fuel cladding tube fracture during LOCA using Bayesian update based on information criteria

*Shusuke Hamaguchi1, Takafumi Narukawa1, Takashi Takata1 (1. UTokyo)

Keywords:LOCA, fuel cladding tube, fractuer limit, information criteria, Bayesian update

To ensure reactor safety during a loss-of-coolant accident (LOCA), it is necessary to precisely evaluate the fracture limit of the fuel cladding tube during the LOCA. We propose a method to effectively improve the prediction accuracy of the fracture using Bayesian update with additional data that are obtained based on information criteria.