Research field (4):
Nuclear fusion
, Nuclear engineering
, Structural and functional materials
, Metallic materials
Research theme for competitive and other funds (17):
2020 - 2025 核融合炉で使用後10年以内に再利用可能な低放射化バナジウム合金の試作開発
2019 - 2022 Exploring the missing link in irradiation embrittlement using ultra-small testing technologies
2019 - 2021 Effects of domain wall on diffusion of defects
2018 - 2021 Modeling tolerance to irradiation embrittlement of reduced activation ODS steels by quantitative specification of nano-mezo structures
2016 - 2019 強度因子の異なる欠陥が混在する組織における材料強度評価モデルの構築
2014 - 2018 A Challenge to Development of Functionally-graded Long-life Divertor based on Degradation Behavior Caused by Thermal Fatigue of Tungsten
2012 - 2017 Development of high durable Tungsten materials to realize divertor of a fusion reactor.
2012 - 2014 Study on mechanism of grain boundary embrittlement of austenitic stainless steel after irradiation using in-situ monitoring system of grain boundary separation
藪内 聖皓, 近藤 創介, 檜木 達也, 笠田 竜太. 複合ビーム材料照射装置DuETを用いた核融合炉材料研究と関連材料研究の展開-Research on Fusion Reactor Materials and Related Materials using the Dual-Beam Facility for Energy Science and Technology DuET. プラズマ・核融合学会誌 = Journal of plasma and fusion research / プラズマ・核融合学会編集委員会 編. 2021. 97. 7. 403-418
LIU Yuchen, 笠田竜太, GAO Zimo, YU Hao, 近藤創介, 藪内聖皓, MOHAMAD Aghamiri, 大野直子, 鵜飼重治, 能登裕之, et al. Instructions for Preparing Manuscripts for JSPF Annual Meeting. プラズマ・核融合学会年会(Web). 2020. 37th
N.Y. Iwata, Y. Morizono, S. Suzuki, K. Yabuuchi, A. Kimura. Development of high ductile ODS ferritic steel for advanced energy system. Proceedings of the 10th International Symposium of Advanced Energy Science, Kyoto, Japan. 2019. 215