Rchr
J-GLOBAL ID：201801015971491413
Update date: Apr. 25, 2024
Takashi Onizawa
オニザワ タカシ | Takashi Onizawa
Affiliation and department：
Research field (1)：
Structural and functional materials
Research theme for competitive and other funds (1)：
- 2021 - 2025 Development of multi-type simultaneous measurement method in radiation field toward the creation of innovative materials
Papers (24)：
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Toyota Kodai, Imagawa Yuya, Onizawa Takashi, Kato Shoichi, Furuya Yoshiyuki*. Validation of the applicability of the best-fit fatigue curves for 550$^{\circ}$C in Mod.9Cr-1Mo steel to 1$\times$10$^{11}$ cycles. Nihon Kikai Gakkai Rombunshu (Internet). 2023. 89. 928. 23-00206\_1-23-00206\_15
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Otsuka Satoshi, Shizukawa Yuta, Tanno Takashi, Imagawa Yuya, Hashidate Ryuta, Yano Yasuhide, Onizawa Takashi, Kaito Takeji, Onuma Masato*, Mitsuhara Masatoshi*, et al. High-temperature creep properties of 9Cr-ODS tempered martensitic steel and quantitative correlation with its nanometer-scale structure. Journal of Nuclear Science and Technology. 2023. 60. 3. 288-298
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Ohshima Hiroyuki, Morishita Masaki*, Aizawa Kosuke, Ando Masanori, Ashida Takashi, Chikazawa Yoshitaka, Doda Norihiro, Enuma Yasuhiro, Ezure Toshiki, Fukano Yoshitaka, et al. Sodium-cooled Fast Reactors. Sodium-cooled Fast Reactors; JSME Series in Thermal and Nuclear Power Generation, Vol.3. 2022. 631
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Toyota Kodai, Onizawa Takashi, Wakai Takashi, Hashidate Ryuta, Kato Shoichi. Material data acquisition activities to develop the material strength standard for sodium-cooled fast reactors. Proceedings of International Conference on Fast Reactors and Related Fuel Cycles; Sustainable Clean Energy for the Future (FR22) (Internet). 2022. 10
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Hashidate Ryuta, Kato Shoichi, Onizawa Takashi, Wakai Takashi, Kasahara Naoto*. Proposal of simulation material test technique for clarifying the structure failure mechanisms under excessive seismic loads. Proceedings of ASME 2021 Pressure Vessels and Piping Conference (PVP 2021) (Internet). 2021. 9
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MISC (15)：
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Imagawa Yuya, Toyota Kodai, Onizawa Takashi, Kato Shoichi. FBR metallic materials test manual (2023 revised edition). JAEA-Testing 2023-004. 2024. 76
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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
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Wakai Takashi, Onizawa Takashi, Obara Satoshi, Nakashima Takashi*, Yokoyama Tetsuo*, Iseda Atsuro*, Ogumo Shinya*, Futagami Satoshi*. Manufacturability and strength assessment of modified 9Cr-1Mo steel products for Japan sodium cooled fast reactor components, 2; Long thin-walled tubes with small diameter. Tainetsu Kinzoku Zairyo Dai-123-Iinkai Kenkyu Hokoku. 2011. 52. 2. 171-181
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Wakai Takashi, Onizawa Takashi, Ando Masanori, Aoto Kazumi, Martin L.*. Integrity assessment of aged and on-site welded joints in LMFR. Proceedings of Creep and Fracture in High Temperature Components-design and life Assessment Issues (CD-ROM). 2005. 11
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Onizawa Takashi, Wakai Takashi, Ando Masanori, Aoto Kazumi. Effect of V and Nb contents on mechanical properties of high Cr steel. Proceedings of Creep and Fracture in High Temperature Components-Design and Life Assessment Issues. 2005. 12
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Lectures and oral presentations (42)：
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Development of fatigue testing techniques using solid round bar miniature specimens
(日本金属学会2024年春期(第174回)講演大会)
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Thermal aging effects on high temperature tensile properties of Mod.9Cr-1Mo steel
(日本金属学会2024年春期(第174回)講演大会)
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Development of the material strength standard of 316FR steel and modified 9Cr-1Mo steel for next-generation fast reactor in Japan
(27th International Conference on Structural Mechanics in Reactor Technology (SMiRT 27))
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Structural design and materials technology for fast reactors and high temperature gas-cooled reactors; Structural design and materials technology for fast reactors
(日本溶接協会第57回国内シンポジウム)
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Characterization of iron-based and tungsten-based high-entropy alloys
(Nuclear Materials Conference 2022 (NuMat 2022))
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