Rchr
J-GLOBAL ID:201801005287750617   Update date: Oct. 10, 2024

Miyazawa Takeshi

ミヤザワ タケシ | Miyazawa Takeshi
Affiliation and department:
Research field  (2): Nuclear engineering ,  Nuclear fusion
Research keywords  (8): 組織制御 ,  高温強度 ,  燃料被覆管 ,  酸化物分散強化型鋼 ,  原子力材料 ,  高融点金属材料 ,  照射効果 ,  核融合炉材料、照射効果
Research theme for competitive and other funds  (5):
  • 2021 - 2024 タングステン合金の照射誘起高靭性化に資する組織形成機構の解明
  • 2017 - 2022 Devrlopment of high durable Tungsten materials to realize divertor of a fusion reactor.
  • 2018 - 2021 Challenge to predict material degradation for tungsten under fusion neutron irradiation
  • 2015 - 2016 低放射化バナジウム合金の高温強度向上と低温照射脆化抑制の両立
  • 2012 - 2013 超微小試験による耐照射性バナジウム合金の照射硬化評価とバルク材変形特性の予測
Papers (31):
  • 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
  • Takeshi Miyazawa, Yuta Kikuchi, Masami Ando, Ju-Hyeon Yu, Kiyohiro Yabuuchi, Takashi Nozawa, Hiroyasu Tanigawa, Shuhei Nogami, Akira Hasegawa. Microstructural evolution in tungsten binary alloys under proton and self-ion irradiations at 800°C. Journal of Nuclear Materials. 2023. 154239-154239
  • Takeshi Miyazawa, Haruka Saito, Yoshimitsu Hishinuma, Takuya Nagasaka, Takeo Muroga, Jingjie Shen, Yasuki Okuno, Hao Yu, Ryuta Kasada, Akira Hasegawa. Effect on impact properties of adding tantalum to V-4Cr-4Ti ternary vanadium alloy. Nuclear Materials and Energy. 2022. 31. 101198-101198
more...
MISC (2):
Lectures and oral presentations  (4):
  • Study on tensile and creep deformation mechanisms of 9Cr-ODS steels at ultra-high temperatures
    (東北大学金属材料研究所大洗・アルファ合同研究会)
  • Effectiveness of accelerator irradiation and necessity of materials irradiation reactor in fusion reactor material development; Irradiation tolerance evaluation of advanced tungsten alloys
    (日本金属学会第1回若手研究グループ「原子力エネルギー用材料研究会」)
  • 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)
  • Neutron Irradiation Effects on Mechanical Properties of Tungsten Alloys
    (The 19th International Conference on Fusion Reactor Materials 2019)
Education (2):
  • 2009 - 2014 The Graduate University for Advanced Studies School of Physical Sciences Department of Fusion Science
  • 2005 - 2009 Tokyo University of Science Faculty of Science, Division 1 Applied Physics
Professional career (1):
  • 工学博士(核融合科学専攻) (The Graduate University for Advanced Studies)
Work history (5):
  • 2022/04 - 現在 Japan Atomic Energy Agency
  • 2017/06 - 2022/03 Tohoku University Graduate School of Engineering Department of Quantum Science and Energy Engineering
  • 2016/04 - 2017/05 National Institutes for Quantum and Radiological Science and Technology
  • 2015/06 - 2016/03 Japan Atomic Energy Agency
  • 2014/04 - 2015/05 National Institute for Fusion Science
Committee career (1):
  • 2018/04 - 2020/03 日本原子力学会材料部会 庶務幹事
Awards (7):
  • 2021/09 - 核融合エネルギーフォーラム 2021年度吉川允二記念核融合エネルギー奨励賞 核融合ダイバータ設計に資する先進タングステン合金の中性子照射脆化耐性に関する研究
  • 2019/09 - 日本原子力学会核融合工学部会 第16回核融合工学部会賞奨励賞 核融合炉ダイバータ用タングステン合金の中性子照射環境下における劣化挙動
  • 2019/05 - 日本原子力学会東北支部 平成30年度東北支部奨励賞 核融合炉ダイバータ用タングステン材料の照射環境下における劣化挙動
  • 2018/12 - プラズマ・核融合学会 第35回年会若手優秀発表賞 熱中性子遮蔽を施して照射したタングステンとタングステン合金の機械特性
  • 2014/09/19 - The 12th Japan-China Symposium on Materials for Advanced Energy Systems and Fission and Fusion Engineering JCS-12 Young Researcher Award
Show all
Association Membership(s) (2):
日本原子力学会 ,  THE JAPAN INSTITUTE OF METALS AND MATERIALS
※ Researcher’s information displayed in J-GLOBAL is based on the information registered in researchmap. For details, see here.

Return to Previous Page