Yamashita Shinichiro

ヤマシタシンイチロウ | Yamashita Shinichiro

Affiliation and department：

Research field (3)： Nuclear engineering , Structural and functional materials , Nuclear engineering

Research keywords (3)：軽水炉 , 照射損傷 , Nuclear Material

Research theme for competitive and other funds (10)：

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Papers (79)：

Ukai Shigeharu, Sakamoto Kan*, Otsuka Satoshi, Yamashita Shinichiro, Kimura Akihiko*. Alloy design and characterization of a recrystallized FeCrAl-ODS cladding for accident-tolerant BWR fuels; An Overview of research activity in Japan. Journal of Nuclear Materials. 2023. 583. 154508\_1-154508\_24
Ukai Shigeharu, Yamashita Shinichiro. Dislocation-climbing bypass over dispersoids with different lattice misfit in creep deformation of FeCrAl oxide dispersion-strengthened alloys. Journal of Materials Research and Technology. 2022. 16. 891-898
K. Sakamoto, Y. Miura, S. Ukai, N.H. Oono, A. Kimura, A. Yamaji, K. Kusagaya, S. Takano, T. Kondo, T. Ikegawa, et al. Development of accident tolerant FeCrAl-ODS fuel cladding for BWRs in Japan. Journal of Nuclear Materials. 2021. 557. 153276-153276
S.M.S. Aghamiri, T. Sugawara, S. Ukai, N. Oono, K. Sakamoto, S. Yamashita. Orientation dependence of yield strength in a new single crystal-like FeCrAl oxide dispersion strengthened alloy. Materials Characterization. 2021. 176. 111043-111043
S. M.S. Aghamiri, T. Sowa, S. Ukai, N. Oono, K. Sakamoto, S. Yamashita. Microstructure and texture evolution and ring-tensile properties of recrystallized FeCrAl ODS cladding tubes. Materials Science and Engineering A. 2020. 771

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MISC (64)：

Yamashita Shinichiro. Current status of accident tolerant fuel (ATF) development, 1; Overview of ATF development conducted under the technology development project for improving nuclear safety. Nihon Genshiryoku Gakkai-Shi ATOMO$\Sigma. 2023. 65. 4. 233-237
岡弘, 橋本直幸, 礒部繁人, 山下真一郎. 73dpaまでイオン照射した低放射化ハイエントロピー合金の組織変化. 日本金属学会講演大会(Web). 2022. 170th
岡弘, 佐藤幹, 橋本直幸, 礒部繁人, 山下真一郎. Development of new reduced activation HEAs by additive manufacturing method (2) Material property of additively manufactured alloys. 日本原子力学会秋の大会予稿集(CD-ROM). 2021. 2021
山下真一郎, 井岡郁夫, 岡弘, 礒部繁人, 橋本直幸. Development of new reduced activation HEAs by additive manufacturing method (3) Radiation property. 日本原子力学会秋の大会予稿集(CD-ROM). 2021. 2021
橋本直幸, 上田幹人, 林重成, 岡弘, 礒部繁人, 山下真一郎, 板倉充洋, 都留智仁. Development of new reduced activation HEAs by additive manufacturing method (1) Outline. 日本原子力学会秋の大会予稿集(CD-ROM). 2021. 2021

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Patents (2)：

Lectures and oral presentations (185)：

Study on coating technic to enhance accident tolerance of fuel cladding, 2; Oxidation and hydriding behavior of the Cr coated Zry4
(日本原子力学会2024年春の年会)
Study on coating technic to enhance accident tolerance of fuel cladding, 4; Oxidation behavior of the TiN/TiAlN multilayer coated Zry-4
(日本原子力学会2024年春の年会)
Study on coating technic to enhance accident tolerance of fuel cladding, 1; Overview of accident tolerant coating technic studies and apparatus development in JAEA
(日本原子力学会2024年春の年会)
Formation behavior of Cr-rich phases in Fe-Cr-Al alloys by thermal ageing and its relation to mechanical properties
(日本金属学会2024年春期(第174回)講演大会)
Study on coating technic to enhance accident tolerance of fuel cladding, 3; Irradiation behavior of the Cr coated MDA cladding
(日本原子力学会2024年春の年会)

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Professional career (1)：

Work history (6)：

2023/04 - 現在 Hokkaido University Graduate School of Engineering Guest Professor
2022/04 - 現在 Japan Atomic Energy Agency Nuclear Engineering Science Center Principal Researcher
2016/04 - 2022/03 Japan Atomic Energy Agency
- 2016/03 Japan Atomic Energy Agency
- 2015/06 Japan Atomic Energy Agency

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Committee career (4)：

2023/04 - 現在一般社団法人日本電気協会原子力規格委員会原子燃料分科会委員
2020/09 - 2023/09 Jules Horowitz Materials Testing Reactor Governing Board International Scientific Advisory Group Member
2015/04 - 2017/03 一般社団法人日本原子力学会材料部会国際学術小委員
2007/04 - 2009/03 一般社団法人日本原子力学会材料部会庶務幹事

Association Membership(s) (3)：

公益社団法人腐食防食学会 , 公益社団法人日本金属学会 , 一般社団法人日本原子力学会

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