2023年秋の大会

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V. 核燃料サイクルと材料 » 501-2 核燃料とその照射挙動

[2C01-07] データ科学・機械学習による燃料研究

2023年9月7日(木) 09:30 〜 11:25 C会場 (IB電子情報館1F IB015)

座長:有馬 立身(九大)

10:30 〜 10:45

[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)

キーワード: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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