Rchr
J-GLOBAL ID：201701016520609959
Update date: Sep. 24, 2024
YU HAO
ユウ ハオ | YU HAO
Affiliation and department：
Homepage URL (1)：
http://web.tohoku.ac.jp/imr-numat/
Research field (3)：
Thin-film surfaces and interfaces
, Structural and functional materials
, Metallic materials
Research keywords (4)：
Nuclear materials
, High temperature oxidation
, Mechanical properties
, Oxide dispersion strengthening
Research theme for competitive and other funds (7)：
- 2023 - 2026 照射脆化耐性を向上する析出相強靭化法の開発とローカルアプローチによるモデル化
- 2023 - 2026 Structural integrity engineering of FeCrAl-ODS in lead-cooled SMR under superimposed stress-corrosion environment
- 2023 - 2025 Improvement of Radiation Resistance of Alumina Scales Formed on FeCrAl ODS Alloys by Microstructure Control
- 2021 - 2024 酸化物分散強化銅合金の大型化に関するフィージビリティ研究
- 2021 - 2023 変形誘起ナノ双晶と酸化物分散強化を利用した高延性高強度アルミナフォーミングCoNiCrAl合金の創製
- 2019 - 2022 超微小試験技術による照射脆化のミッシングリンク解明
- 2018 - 2020 Irradiation effects on the performance of the alumina scale formed in FeCrAl ODS ferritic steels
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Papers (46)：
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Hao Yu, Toshiki Saito, Zimo Gao, Yasuyuki Ogino, Sosuke Kondo, Ryuta Kasada, Hiroyuki Noto, Yoshimitsu Hishinuma, Suguru Matsuzaki. Feasibility study on mass-production of oxide dispersion strengthened Cu alloys for the divertor of DEMO fusion reactor. Journal of Nuclear Materials. 2024. 599
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Hao Yu, Sosuke Kondo, Yasuyuki Ogino, Ryuta Kasada. The Role of Y2O3/Hf Co-Doping on the Microstructure and Tensile Properties of Alumina-Forming Co-Cr-Al-Ni ODS Superalloy. Materials Transactions. 2024. 65. 8. 867-875
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Size dependence of micro-scale mechanical properties on heavy-ion irradiated tempered-martensitic steel evaluated through nanoindentation and micropillar compression tests. Journal of Nuclear Materials. 2024. 593
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Evaluation of the strength of FeCrAl alloy/surface Oxide film interface by micro double-notch shear test. Fusion Engineering and Design. 2024. 201
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Toshiki Saito, Hao Yu, Zimo Gao, Koji Inoue, Sosuke Kondo, Ryuta Kasada, Yasuyoshi Nagai, Yojiro Oba, Kosuke Hiroi. Multiscale observation of nano-oxide particles in oxide-dispersion-strengthened Cu alloys. Journal of Alloys and Compounds. 2024. 983. 173852
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MISC (28)：
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野呂崇史, 笠田竜太, YU Hao, GENG Diancheng, 近藤創介, 熊野秀樹, 遠藤美奈子. Study on the local mechanical properties at the interface of RPV cladding. 日本原子力学会春の年会予稿集(CD-ROM). 2023. 2023
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板垣克, 板垣克, 笠田竜太, 近藤創介, 耿殿程, 耿殿程, 余浩, 陣場優貴, 陣場優貴. Fe2M Laves相の機械的特性. 日本金属学会講演大会(Web). 2023. 173rd
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松戸玲菜, 松戸玲菜, 水元希, 水元希, 耿殿程, 耿殿程, 余浩, 近藤創介, 笠田竜太. Cr23C6およびCr23B1C5の機械的性質および変形挙動に及ぼす照射の影響. 日本金属学会講演大会(Web). 2023. 173rd
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古川雄磨, 古川雄磨, GENG Diancheng, GENG Diancheng, 近藤創介, 余浩, 荻野靖之, 笠田竜太. 低放射化フェライト鋼の押込み硬さの統計的性質に及ぼすサイズ効果. 日本金属学会講演大会(Web). 2023. 173rd
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余浩, 近藤創介, 荻野靖之, 笠田竜太. Effect of irradiation on the fracture performance and adhesion strength of alumina scales formed on FeCrAl ferritic ODS alloys. 日本金属学会講演大会(Web). 2023. 173rd
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Patents (1)：
Lectures and oral presentations (30)：
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ダイバータ用酸化物分散強化型Cu合金の大型生産の実現へ
(第15回核融合エネルギー連合講演会 2024)
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Feasibility study on mass- production of oxide dispersion strengthened Cu alloys for the divertor of DEMO fusion reactor,
(21st International Conference on Fusion Reactor Materials (ICFRM-21) 2023)
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Co-doping Y/Hf on the oxidation behavior of alumina-forming Co-based oxide dispersion strengthened superalloys
(金属学会 2023 年春期(第 172 回)講演大会 2023)
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Effect of irradiation on the fracture performance and adhesion strength of alumina scales formed on FeCrAl ferritic ODS alloys
(金属学会 2023 年秋期(第 173 回)講演大会 2023)
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Effect of Fe ion irradiation on the performance of alumina scale formed on FeCrAl ODS ferritic alloys
(The 31th International Toki Conference on Plasma and Fusion Research (ITC31) 2022)
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Awards (6)：
Association Membership(s) (3)：
プラズマ・核融合学会
, 日本原子力学会
, THE JAPAN INSTITUTE OF METALS AND MATERIALS
