2023 Fall Meeting

Presentation information

Oral presentation

V. Nuclear Fuel Cycle and Nuclear Materials » 501-2 Nuclear Fuel and the Irradiation Behavior

[2C01-07] Data Science, Fuel Research with Machine Learning

Thu. Sep 7, 2023 9:30 AM - 11:25 AM Room C (IB Bildg.1F IB015)

Chair:Tatsumi Arima(Kyushu Univ.)

10:30 AM - 10:45 AM

[2C05] New Developments in Nuclear Fuel Research through Integration with Data Science

(5)Fabrication and Characterization of Metallic Uranium Compounds (UFe3B2, USiNi) Prepared via Spark Plasma Sintering

*Yifan Sun1, Yuji Miyawaki2, Yuji Ohishi2, Hiroaki Muta2, Shun Fujieda2, Ken Kurosaki1,3 (1. Kyoto Univ., 2. Osaka Univ., 3. Univ. of Fukui)

Keywords:Advanced nuclear fuels, Machine learning, Thermal conductivity

To accelerate the discovery of advanced nuclear fuels exhibiting superior thermal conductivity, we constructed a machine learning (ML) model to predict the thermal conductivity of uranium-based compounds. To evaluate the reliability of our ML model, we need to compare the predicted thermal conductivities with experimental data. In this study, dense UFe3B2and USiNi samples were fabricated through spark plasma sintering and their thermal conductivities were assessed using laser flash analysis. A comparison of the measured and predicted thermal conductivities of UFe3B2 revealed that the model accurately predicted both the thermal conductivity and its temperature dependence. Conversely, for USiNi, the model only accurately predicted the temperature dependence but overestimated the thermal conductivity. Overall, our preliminary findings highlight the potential of ML as a transformative tool in the discovery of novel nuclear fuels.

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