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 (123)：
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
Masatoshi Mitsuhara, Koichi Kurino, Yasuhide Yano, Satoshi Ohtsuka, Takeshi Toyama, Masato Ohnuma, Hideharu Nakashima. High Temperature Mechanical Properties and Microstructure in 9Cr or 12Cr Oxide Dispersion Strengthened Steels. Tetsu-to-Hagane. 2023. 109. 3. 189-200
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
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)
