Rchr
J-GLOBAL ID：201901002340041400   Update date: Nov. 12, 2024

Ohtsuka Satoshi

Ohtsuka Satoshi
Affiliation and department：
Japan Atomic Energy Agency

About Japan Atomic Energy Agency


Research field  (1)： Metallic materials
Research keywords  (7)： Microstructure control ,  Irradiation properties ,  High temperature strength ,  fuel cladding tube ,  oxide dispersion strengthened steel ,  Fast reactor fuels and materials ,  Nuclear materials
Research theme for competitive and other funds  (2)：
  • 2019 - 2023 Development of irradiation properties evaluation technique of accident tolerant fuel cladding tube for advanced nuclear system
  • 2007 - 2010 Synthesis of Oxide Dispersion Strengthened Composite Materials
Papers (125)：
  • Toyama Takeshi*, Tanno Takashi, Yano Yasuhide, Inoue Koji*, Nagai Yasuyoshi*, Otsuka Satoshi, Miyazawa Takeshi, Mitsuhara Masatoshi*, Nakashima Hideharu*, Onuma Masato*, et al. Oxide particles in oxide dispersion strengthened steel neutron-irradiated up to 158 dpa at Joyo. Journal of Nuclear Materials. 2024. 599. 155252\_1-155252\_14
  • Takeshi Miyazawa, Takashi Tanno, Yuya Imagawa, Ryuta Hashidate, Yasuhide Yano, Takeji Kaito, Satoshi Ohtsuka, Masatoshi Mitsuhara, Takeshi Toyama, Masato Ohnuma, et al. Formulation of high-temperature strength equation of 9Cr-ODS tempered martensitic steels using the Larson-Miller parameter and life-fraction rule for rupture life assessment in steady-state, transient, and accident conditions of fast reactor fuel. Journal of Nuclear Materials. 2024. 155008-155008
  • Yuya Imagawa, Ryuta Hashidate, Takeshi Miyazawa, Takashi Onizawa, Satoshi Ohtsuka, Yasuhide Yano, Takashi Tanno, Takeji Kaito, Masato Ohnuma, Masatoshi Mitsuhara, et al. Creep deformation and rupture behavior of 9Cr-ODS steel cladding tube at high temperatures from 700°C to 1000°C. Journal of Nuclear Science and Technology. 2023
  • 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
  • Yasuhide Yano, Tomoyuki Uwaba, Takashi Tanno, Tsunemitsu Yoshitake, Satoshi Ohtsuka, Takeji Kaito. Tensile properties of modified 316 stainless steel (PNC316) after neutron irradiation over 100 dpa. Journal of Nuclear Science and Technology. 2023. 1-9
ｍore...
MISC (73)：
  • Miyazawa Takeshi, Uwaba Tomoyuki, Yano Yasuhide, Tanno Takashi, Otsuka Satoshi, Onizawa Takashi, Ando Masanori, Kaito Takeji. High-temperature strength of modified type 316 steel for fast reactor fuel before and after neutron irradiation. JAEA-Technology 2024-009. 2024. 140
  • Yano Yasuhide, Hashidate Ryuta, Tanno Takashi, Imagawa Yuya, Kato Shoichi, Onizawa Takashi, Ito Chikara, Uwaba Tomoyuki, Otsuka Satoshi, Kaito Takeji. Evaluation of tensile and creep properties on 9Cr-ODS steel claddings. JAEA-Data/Code 2021-015. 2022. 64
  • Otsuka Satoshi, Kaito Takeji. Challenge next-generation nuclear system; Development of oxide dispersion strengthened ferritic steel. Enerugi Rebyu. 2019. 39. 1. 44-46
  • 笠井将樹, 鵜飼重治, 大野直子, 林重成, 大塚智史. 9CrODS鋼におけるマッシブ変態の集合組織制御. 日本鉄鋼協会日本金属学会両支部合同冬季講演大会概要集. 2019. 2018
  • Satoshi Ohtsuka, Takashi Tanno, Hiroshi Oka, Yasuhide Yano, Shoichi Kato, Tomohiro Furukawa, Takeji Kaito. Model calculation of Cr dissolution behavior of ODS ferritic steel in high-temperature flowing sodium environment (vol 505, pg 44, 2018). JOURNAL OF NUCLEAR MATERIALS. 2018. 510. 661-661
ｍore...
Patents (23)：
  • 酸化物分散強化型焼き戻しマルテンサイト鋼の製造方法
  • ACIER MARTENSITIQUE TREMPE RENFORCE PAR DISPERSION D'OXYDES D'EXCELLENTE RESISTANCE A LA CORROSION, TENACITE ET PROPRIETE MECANIQUES A TEMPERATURE ELEVEE, ET PROCEDE DE PRODUCTION DE CELUI-CI
  • 酸化物分散強化型鋼およびその製造方法
  • スーパーODS鋼
  • 粗大結晶粒組織を有する高温クリープ強度に優れたフェライト系酸化物分散強化型鋼の製造方法
ｍore...
Lectures and oral presentations  (112)：
  • Development of irradiation properties evaluation technique of accident tolerant fuel cladding tube for advanced nuclear system
    (令和5年度原子力システム研究開発事業成果報告会)
  • Applicability evaluation of Larson-Miller parameter (LMP)-Life fraction rule to high-temperature strength of 9Cr-ODS steels
    (日本金属学会2023年春期(第172回)講演大会)
  • The Difference of grain growth in 9Cr-ODS and 11Cr-F/M steels at ultra-high temperatures
    (日本金属学会2023年春期(第172回)講演大会; 第73回金属組織写真賞作品)
  • Development and issues of fast reactor core materials
    (日本原子力学会2022年秋の大会)
  • Nanocluster evolution in 9Cr ODS steel after high-dose neutron irradiation in Joyo
    (日本金属学会2022年秋期(第171回)講演大会)
ｍore...
Professional career (1)：
  • Dr.Eng. (Tohoku university)
Work history (4)：
  • 2020/04 - 現在 Japan Atomic Energy Agency Section manager
  • 2014/07 - 2017/03 Japan Atomic Energy Agency Principal Researcher
  • 2009/07 - 2014/06 Japan Atomic Energy Agency Assistant Principal Researcher
  • 2000/04 - Japan Nuclear Cycle Development Institute
Association Membership(s) (2)：
THE JAPAN INSTITUTE OF METALS AND MATERIALS ,  ATOMIC ENERGY SOCIETY OF JAPAN
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