2022 Annual Meeting

Presentation information

Oral presentation

IV. Nuclear Plant Technologies » 401-2 Operational Management, Inspection and Maintenance of Reactor

[1F12-15] Advanced Management Technology of Reactor Operation Management

Wed. Mar 16, 2022 4:10 PM - 5:20 PM Room F

Chair: Takayuki Miyagawa (JAPC)

4:10 PM - 4:25 PM

[1F12] Development of evaluation method of LOCA break diameter using Gaussian process regression

*Akira Nakamura1, Takayoshi Kusunoki1 (1. INSS)

Keywords:machine learning, PWR, loss of coolant accident, numerical simulation

The method to predict LOCA break diameter automatically from the reactor coolant pressure has been developed in this research. This report describes the learning result using Gaussian process regression and the features extracted from the RCS pressure calculated by MAAP4 in order to improve prediction accuracy.