Otsuka Teppei

オオツカテッペイ | Otsuka Teppei

Affiliation and department：
Job title： Professor

Research field (4)： Nuclear fusion , Structural and functional materials , Nuclear engineering , Metallic materials

Research keywords (21)：水素 , 重水素 , トリチウム , 炭素14 , 核融合炉材料 , 原子力材料 , 鉄鋼材料 , 水素吸蔵合金 , 燃料電池システム , 放射線電池 , イメージングプレート , トリチウムオートラジオグラフィ , 地層処分 , プラズマー壁相互作用 , トリチウムリテンション , 核融合炉ダスト , 水素脆性 , High temperature oxidation , 透過係数 , 拡散係数 , 溶解度

Research theme for competitive and other funds (11)：

2021 - 2024 Design and production of tritium production test modules for irradiation test using High Temperature engineering Test Reactor
2018 - 2021 Study on tritium-production test and design of the Li-loading rod using HTTR for fusion reactors
2015 - 2018 Development of Li-loading rod of high-temperature gas-cooled reactor for tritium production
2014 - 2018 Measurement of Tritium Distributions on Divertor Tiles used in JET-ITER Like Wall Experiments
2014 - 2018 Tritium permeation induced by water corrosion of metals

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Papers (85)：

Y. Torikai, G. Kikuchi, A. Owada, S. Masuzaki, T. Otsuka, N. Ashikawa, M. Yajima, M. Tokitani, Y. Oya, S.E. Lee, et al. Overview of tritium retention in divertor tiles and dust particles from the JET tokamak with the ITER-like wall. Nuclear Fusion. 2023. 64. 1. 016032-016032
Hideaki Matsuura, Taisei Abe, Kanta Kitagawa, Motomasa Naoi, Hiromi Kawai, Kazunari Katayama, Teppei Otsuka, Minoru Goto, Shigeaki Nakagawa, Etsuo Ishitsuka, et al. T production using a high-temperature gas-cooled reactor for the DEMO fusion reactor: Li rod structure for the initial irradiation test. Fusion Engineering and Design. 2023. 197. 114054-114054
Yuki Koga, Hideaki Matsuura, Kazunori Katayama, Teppei Otsuka, Minoru Goto, Shimpei Hamamoto, Etsuo Ishitsuka, Shigeaki Nakagawa, Kenji Tobita, Youji Someya, et al. Loading method of Li rods for tritium production using High-Temperature Gas-Cooled reactor for fusion reactors. Nuclear Engineering and Design. 2023. 415. 112665
Teppei Otsuka, Ryo Hatano, Masashi Inoue, Alexander Potekhin, Kirill Klimov. Deuterium permeation through liquid tin supported by a nickel substrate. Fusion Engineering and Design. 2023. 193
S. Lee, Y. Hatano, S. Masuzaki, Y. Oya, M. Tokitani, M. Yajima, T. Otsuka, N. Ashikawa, Y. Torikai, N. Asakura, et al. Tritium distributions in castellated structures of Be limiter tiles from JET-ITER-like wall experiments. Nuclear Fusion. 2023. 63. 4. 046023-046023

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MISC (2)：

大矢恭久, 小林真, 大塚哲平, 片山一成, 信太祐二, 山内有二, 原正憲, 波多野雄治, 島田雅, BUCHENAUER Dean, et al. 高温中性子照射したタングステン中における水素同位体挙動. 核融合エネルギー連合講演会(CD-ROM). 2018. 12th
渥美寿雄, 波多野雄治, 庭瀬敬右, 車田亮, 大塚哲平. 中性子による炭素材料の特性変化と核融合炉への適応性評価. 東北大学金属材料研究所附属量子エネルギー材料科学国際研究センター共同利用研究経過報告書(CD-ROM). 2017. 34

Lectures and oral presentations (155)：

キャパシタ型γ線電池の充電特性
(アイソトープ・放射線研究発表会 2022)
Study on T-production Li rod for HTGR~Li rod Structure and Loading Method Considering Reactor Core Heterogeneity~
(日本原子力学会春の年会予稿集(CD-ROM) 2021)
Tritium permeation behaviors through the interface of F82H/water
(日本原子力学会春の年会予稿集(CD-ROM) 2021)
Compatibility test of tritium permeation barrier coatings with pressurized water
(日本原子力学会春の年会予稿集(CD-ROM) 2021)
Development of Measurement Technique of Tritium Retention in Fine Particles and Its Application to Dust in JET with ITER-like Wall
(2020)

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Works (1)：

ギガサイクル疲労破壊機構に及ぼす水素の影響と疲労強度信頼性向上方法の確立
2003 -

Professional career (1)：

(BLANK)

Work history (3)：

2022/04 - 現在 Kindai University
2016/04 - 2022/03 Kindai University Faculty of Science and Engineering Associate Professor
1999/04 - 2016/03 Kyushu University

Committee career (2)：

2018/04 - 2020/07 プラズマ・核融合学会プラズマ・核融合学会学会誌編集委員会
2017/04 - 2019/03 日本原子力学会核融合工学部会庶務幹事プログラム編集委員

Awards (2)：

2022/11 - プラズマ・核融合学会技術進歩賞微粒子に蓄積するトリチウムの測定技術開発とJETで生成されたダスト分析への適用
2018/09 - 日本金属学会論文賞

Association Membership(s) (3)：

The Japan Society of Plasma Science and Nuclear Fusion Research , 日本金属学会 , 日本原子力学会

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